W3P87-0969, Cycle 2 Reload Startup Test Rept for Period Ending 870301

Cycle 2 Reload Startup Test Rept for Period Ending 870301

ML20206F343
Person / Time
Site:	Waterford
Issue date:	03/01/1987
From:	Cook K LOUISIANA POWER & LIGHT CO., NEW ORLEANS PUBLIC SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
W3P87-0969, W3P87-969, NUDOCS 8704140219
Download: ML20206F343 (23)

Text

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LOUISIANA POWER & LIGHT COMPANY WATERFORD STEAM ELECTRIC STATION UNIT 3 CYCLE 2 RELOAD STARTUP TEST REPORT FOR THE PERIOD ENDING MARCH 1, 1987 LICENSE NO. NPF-38 8704140219 070301 PDR ADOCK 050003E2 p PDR 4'

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TABLE OF CONTENTS Page

1.0 INTRODUCTION

3 2.0 PRE-CRITICAL TEST 2.1 Control Element Assembly Trip Test 4 3.0 LOW POWER PHYSICS TESTS 3.1 Critical Boron Concentration 5 3.2 Ten,perature Reactivity Coefficient 6

) 3.3 CEA Reactivity Worth 7 l 4.0 POWER ASCENSION TESTS 4.1 Reactor Coolant Flow Measurement 8 4.2 Fuel Symmetry Verification 9 4.3 Core Power Distribution 9 4.4 Shape Annealing Matrix and Boundary Point Power Correlation Coefficients Verification 10 4.5 Radial Peaking Factor and CEA Shadowing Factor Verification 11 4.6 Temperature Shadowing Factor Verification 12 4.7 Reactivity Coefficients at Power 12

5.0 CONCLUSION

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LIST OF ATTACIDIENTS Page Attachment 1 - CEA Group Reactivity Worth Results 15 Attachment 2 - 68% Power Plateau Radial Power Distribution 16 Attachment 3 - 68% Power Plateau Axial Power Distribution 17 Attachment 4 - 100% Power Plateau Radial Power Distribution 18 Attachment 5 - 100% Power Plateau Axial Power Distribution 19 Attachment 6 - ARO Peaking Factor Results 20 Attachment 7 - Radial Peaking Factor and CEA Shadowing Factor Results 21 a

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1.0 INTRODUCTION

This report describes the WSES-3 Cycle 2 reload startup test program.

The post fuel load startup test program was performed to verify that core performance was consistent with the engineering design and safety analyses.

Some of the tests also provided the data needed for adjustment of addressable constants on the Core Protection Calculators (CPCs).

Post fuel load startup testing of Waterford-3 commenced February 2,1987 with the performance of pre-critical tests. Low power physics testing began on February 4, 1987 at 10:19 a.m. when initial criticality for Cycle 2 was achieved. Low power physics testing was completed on February 6, 1987 at which time power ascension testing commenced. The first intermediate testing plateau (68% full power) was attained on February 10, 1987. Due to a projected positive MTC at 70% power, power was main-tained below 70% until an emergency Tech. Spec. change was received on February 13, 1987 that allowed Special Test Exception 3.10.2 to be invoked in Mode 1. Power was increased to approximately 84% power that evening and remained there until completion of a Moderator Temperature Coefficient measurement on February 20, 1987. Full power was attained on February 21, 1987 and full power testing was completed on February 27, 1987.

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2.0 PRE-CRITICAL TEST 2.1 CONTROL ELEMENT ASSEMBLY (CEA) TRIP TEST Purpose The CEA trip test was performed to verify that the elapsed time between initiation of a CEA trip and 90% insertion was within Technical Specification limits.

Method Hot, full flow conditions were established with Tavg greater than j 525 deg F and all four reactor coolant pumps running. The shutdown CEA groups were withdrawn in the Manual Group mode. Withdrawal was halted at several pre planned intervals to collect inverse count rate data to ensure that the reactor was kept sub-critical. Following shutdown group withdrawal, the regulating groups were withdrawn (also with pre planned holds for count rate data collection) in the Manual Sequential mode. When all CEAs were withdrawn, special Control Element Assembly Calculator software was used to initiate a reactor trip and to record the drop times of each CEA.

Results and Evaluation The measured CEA drop time of each full length CEA from fully with-drawn to 90% inserted was less than the Technical Specification limit of 3.0 seconds.

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3.0 LOW POWER PHYSICS TESTS 3.1 CRITICAL BORON CONCENTRATION (CBC)

Purpose The CBC was obtained for the All Rods Out (ARO) condition and for a partially rodded configuration (Group B inserted). The actual CBC measurements were compared to predictions to verify design, fabrica-tion, and proper loading of the core.

Method Following criticality, the reactor was brought to an essentially unrodded condition and boron concentration was allowed to equilibrate.

The CBC was calculated by correcting the measured equilibrium boron concentration for deviation of CEA position from the AR0 condition.

Following completion of the Group B reactivity worth measurement, boron concentration was again allowed to equilibrate and the CBC for the condition was calculated by correcting the measured equilibrium boron concentration for any deviation of CEA position from the Group B fully inserted condition.

Results and Evaluation The measured CBC values for both measurement conditions (presented below) were within acceptance criteria limits (within 100 ppm of the predicted values).

CEA configuration Predicted Measured ARO 1540 ppm 1510 ppm Group B inserted 1312 ppm 1285 ppm NS20630 5

3.2 TEMPERATURE REACTIVITY COEFFICIENT Purpose The isothermal temperature coefficient (ITC) was measured at the Essentially All Rods Out (EAR 0) configuration and at a partially rodded configuration to verify core physics models. In addition, the moderator temperature coefficient (MTC) was calculated from the measured ITC at the EAR 0 condition to satisfy Technical Specification surveillance requirements.

Method The average coolant temperature was varied and the reactivity feedback associated with the temperature change was used to calculate the ITC.

The MTC was calculated by subtracting a predicted value of the fuel temperature coefficient from the measured ITC.

Results and Evaluation The measured ITC at both measurement conditions agreed well with predicted values and met the acceptance criteria (within i0.3 x 10-4 dRho/degF):

Predicted Measured All Rods Out 0.325 0.345 E-4 dRho/degF Group B -0.390 -0.250 E-4 dRho/degF The measured EARO MTC value (0.505 E-4 dRho/degF) was found to be slightly above the Technical Specification zero power limits.

Administrative limits were placed on RCS boron concentration to ensure that the MTC was maintained within the LCO limits.

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1 3.3 CEA REACTIVITY WORTH 3

i Purpose i The reactivity worths of various CEA groups were measured to verify calculations of available shutdown margin. If sufficient agreement

! between the predicted and measured group worth. exists, the CEA l reactivity worths assumed in the shutdown margin safety analyses are i deemed adequate. In addition, the coupling of each CEA to its extension shaft was verified.

Method CEA worths were measured using the CEA Exchange technique. This technique consists of measuring the worth of a " Reference Group" (Group B) via standard boration/ dilution techniques, then exchanging this group with other groups to measure their worths. All full-length CEAs were included in the measurement groups. Each CEA was moved individually and a corresponding reactivity change was noted to verify coupling.

Results and Evaluation The measured group CEA reactivity worths are presented in Attachment

1. The measured values were in good agreement with the predicted values and were well within the acceptance criteria limits (i0.10% dRho or il5% whichever is larger). All CEAs were verified to be coupled.

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1 4.0 POWER ASCENSION TESTING Following completion of the Low Power Physics Test sequence, reactor power was increased in accordance with normal operating procedures. The power ascension was monitored by an off-line NSSS performance and data process-ing computer algorithm. This computer code was periodically executed in parallel with the power ascension to monitor CPC and COLSS performance related to the processed plant data against which they are normally calibrated. Thus the monitoring algorithm ensured conservative CPC and COLSS operation while optimizing overall efficiency of the test program.

4.1 REACTOR COOLANT FLOW Purpose Reactor coolant flow was measured by calorimetric methods at the 68%

and 100% plateaus to satisfy Technical Specifications surveillance requirements.

Method At steady state conditions, sufficient data was collected to determine the enthalpy rise across the core. This information was used along with the secondary calorimetric power to determine a measured RCS flow rate.

Results and Evaluations The measured RCS flow rate was used to calculate flow calibration factors for the CPCs and COLSS so that the CPC flow rate was conser-vative relative to COLSS and the COLSS flow was conservative to the measured flow rate. In addition, the measured RCS flow rates (164.4 M1bm/hr at 68% power and 161.7 M1bm/hr at 100% power) were within the Technical Specification limit of 148 M1bm/hr.

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4.2 FUEL SYMMETRY VERIFICATION Purpose The Fuel Symmetry test was performed to verify that no detectable fuel mis-loadings exist.

Method Fixed incore detector data was examined at approximately 23% power.

Individual instrumented fuel assembly. powers were compared with the symmetric group average power.

Results and Evaluation The individual assembly powers were in close agreement with the symmetric group average and well within the 10% acceptance criteria limit, indicating that no mis-loadings existed.

4.3 CORE POWER DISTRIBUTION Purrose Core power distribution data using fixed incore neutron detectors was used to further verify proper fuel loading and to verify con-sistency between the as-built core and the engineering design models.

Method Steady state reactor power was established at the 68% and the 100%

test plateaus with equilibrium xenon. Incore detector data was then collected and analyzed using the CECOR computer code. Specified power distribution parameters were obtained from the code and compared to predictions to verify the acceptability of the measured power distribution.

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Results and Evaluation Attachments 2 through 6 present the results of the core power distri-bution tests. All acceptance criteria were met.

4.4 SHAPE ANNEALING MATRIX (SAM) AND BOUNDARY POINT POWER CORRELATION COEFFICIENTS (BPPCC) VERIFICATION Purpose Measurement of the SAM and BPPCCs was performed to ensure that the CPC power distribution calculation is adequate.

Method The SAM elements and the BPPCCs were determined from a linear regres-sion analysis of the measured excore detector readings and correspond-ing core power distribution determined from the incore detector signals. This data was collected periodically during the power ascension from 20% to 68% power and was analyzed using the off-line analysis code discussed in section 4.0. The spectrum of axial shapes encountered during the power ascension was adequate for the calcula-tion of the matrix elements.

Results and Evaluation The SAM and BPPCCs were installed into the CPCs after the validity of the CPC power distribution using these new constants was verified using the off-line analysis code.

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4.5 RADIAL PEAKING FACTOR (RPF) AND CEA SRADOWING FACTOR (RSF)

VERIFICATION Purpose

, Performance of this test at 68% power assured conservatism of the RPFs utilized by the CPCs and COLSS in the power distribution algorithms. In addition, this test calculated measured CEA Shadowing Factors for use in adjusting the CPC shadowing factor multipliers.

Methods The RPFs and the RSFs were calculated using fixed incore detector and excore detector data from the following CEA configurations:

- All Rods Out

- Group 6 fully inserted

- Group 6 fully inserted & PLCEAs @ 37.5 in, withdrawn

- PLCEAs @ 37.5 in, withdrawn These measured values were then used to calculated appropriate CPC and/or COLSS constants.

Results and Evaluations The measured radial peaking factors and CEA shadowing factors are presented in Attachment 7. All necessary adjustments to the appro-priate CPC/COLSS constants were made based upon these measured values.

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l 4.6 TEMPERATURE SHADOWING FACTOR VERIFICATION l

Purpose The Temperature Shadowing factor test was performed to verify the i adequacy of the installed CPC TSF constants.

1 Method i

Using ex-core detector and RCS cold leg data collected during the power ascension, the off-line analysis code calculated the temperature shadowing factor for each CPC channel.

Results and Evaluation The measured TSF for each CPC channel is presented below:

CPC Channel Measured TSF i

A 0.0053 B 0.0053 C 0.0050 D 0.0050 These measured values were within the acceptance criteria bounds of 0.0025 to 0.0080.

4.7 REACTIVITY COEFFICIENTS AT POWER Purpose The Isothermal Temperature Coefficient (ITC) was measured to verify core physics models. The moderator temperature coefficient (MTC) was

! measured to satisfy Technical Specification surveillance requirements.

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Methods i

i i The ITC was measured at approximately 82% power by swinging turbine load to alternately increase and decrease core inlet temperature.

The swings in core temperature and power were used along with the predicted power coefficient to calculate the ITC. The predicted

, fuel temperature coefficient was then subtracted from the measured ITC to obtain the MTC. The measured MTC was then used to verify compliance with the Technical Specifications.

1 Results and Evaluation t

i j The results of the ITC and MTC measurements at this power level j agreed very well with the predicted values:

1 Predicted Measured

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1 ITC -0.22 -0.23 E-4 dRho/degF

, MTC -0.09 -0.10 E-4 dRho/degF l'

1 All acceptance criteria were met at the 82% power level. Furthermore,  !

the projection of MTC of 70% power was calculated to be -0.04 E-4 j dRho/degF (which was in compliance with the Technical Specification a

limit).

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5.0 CONCLUSION

S The results of the Waterford-3 Cycle 2 reload test program summarized in this report show that:

1) The core was correctly loaded with regard to the design fuel management plan and there are no detectable anomalies present which would result in unsafe operation of the plant during the length of the cycle.

2) The calculational models utilized in designing the reload core and performing the safety analyses for Cycle 2 adequately predict core behavior for this fuel management pattern.

Therefore, the Waterford-3 Cycle 2 core was demonstrated to be properly fabricated and installed. The unit can be operated in a manner that will not pose an undue risk to the health and safety of the public.

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i ATTACHMENT 1 CEA GROUP REACTIVITY WORTH RESULTS GROUP PREDICTED MEASURED A 2.107 2.088 I

B 1.436 1.415 6+3 1.265 1.309 5+4 1.187 1.194 1

2+1 1.314 2.271 TOTAL 7.309 7.277 i

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l

ATTACHMENT 6 ARO PEAKING FACTOR RESULTS i

PREDICTED MEASURED  % DIFFERENCE 68% POWER:

Fxy 1.59 1.597 -0.47 Fr 1.56 1.525 2.22 Fz 1.22 1.246 -2.13 Fq 1.88 1.902 -1.17 100% POWER:

Fxy 1.56 1.528 2.04 Fr 1.53 1.476 3.53 Fz 1.18 1.173 0.61 Fq 1.82 1.726 5.18

% Difference = Pred. - feas.

• 100 Pred.

Acceptance Criteria Limit : 10%

I W

t i

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NS20630 20

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1 l

ATTACHMENT 7 RADIAL PEAKING FACTOR TEST RESULTS CEA CONFIGURATION DATE BASE MEASURED INSTALLED Fxy Fxy ARM All Rods Out 1.55 1.597 1.0306 PLCEAs at 37.5" wd. 1.60 1.632 1.0303 Group 6 @ LEL 1.65 1.717 1.0514 Gr. 6 @ LEL & PLCEAs 1.70 1.769 1.0513

@ 37.5" wd.

CEA SHADOWING FACTOR RESULTS MEASURED R0D SHADOWING FACTORS CPC CHANNEL CEA CONFIGURATION A B C D PLCEAs @ 37.5" wd. 1.0391 1.0417 1.0410 1.0357 Group 6 @ LEL 1.0944 1.0954 1.0976 1.0909 Gr. 6 @ LEL & PLCEAs 1.0866 1.0894 1.0912 1.0839

@ 37.5" wd.

)

1 NS20630 21 l

l

f .,

/.

, f LOUISIANA POWER & LIGHT COMPANY e Post Office Box 6008 New 0 deans. Louisiana 70174 Mn!2;LC NEW ORLEANS PUBLIC SERVICE INC.

• Post Office Box 60340 New 0 deans. Louisiana 70160 April 8, 1987-W3P87-0969 A4.05 QA U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

SUBJECT:

Waterford SES Unit 3 Docket No. 50-382 Cycle 2 Startup Test Report Gentlemen:

In accordance with the reporting requirements of Section 6.9 of the Technical Specifications, enclosed is tl'e Waterford 3 Cycle 2 Startup Test Report.

Yours very truly,

.s ilN K.WV ookund f Nuclear Safety & Regulatory Affairs Manager KWC/MJM/plm Enclosure cc: E.L. Blake, W.M. Stevenson, G.W. Knighton, J.ll. Wilson, R.D. Martin, NRC Resident Inspector's Office (W3)

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\

k l "AN EQUAL OPPORTUNITY EMPLOYER" l