ML20058G884

Cycle 4 Startup Test Rept

ML20058G884
Person / Time
Site:	Vogtle
Issue date:	11/05/1993
From:	GEORGIA POWER CO.
To:
Shared Package
ML20058G870	List: ML20058G867 ML20058G884
References
NUDOCS 9312100168
Download: ML20058G884 (14)

Text

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t GEORGIA POWER COMPANY '

VOGTLE ELECTRIC GENERATING PLANT P

UNIT 2, CYCLE 4 STARTUP TEST REPORT f

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i TABLE OF CONTENTS SECTION DESCRIPTION PAGE 1.0 Introduction 3

2.0 Unit 2 Cycle 4 Core Refueling 3

3.0 Control Rod Drop Time Measurement 4

4.0 Initial Criticality 4

5.0 All Rods Out Isothermal Temperature Coefficient and Boron Endpoint Measurement 5

6.0 Control and Shutdown Bank Worth Measurements 5

7.0 Startup and Power Ascension 6

8.0 Reactor Coolant System Flow Measurement 6

Table 1 Control Rod Dash Pot Entry Tirnes 7

Table 2 Summary of Control and Shutdown Rod Bank Worth Measurements 8

Table 3 Summary of Power Ascension Flux Map Data 9

Figure 1 Unit 2 Cycle 4 Reference leading Pattern 10 Figure 2 Control Rod locations 11 Figure 3 Burnable Absorber Configurations 12 Figure 4 Secondary Source Rod Configuration 13 Figure 5 Burnable Absorber and Source Rod locations 14 2

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1.0 INTRODUCTION

The Vogtle Electric Generating Plant Startup Test Report summanzcs results for tests performed as required by plant procedures following a core refueling. The report provides a brief synopsis of each test and gives a comparison of measured values with design parameters, Technical Specifications, or values assumed in the FSAR safety analysis.

Unit 2 is a four loop Westinghouse PWR which is rated at 3565 MWth. The cycle 4 core loading consists of 19317 x 17 fuel assemblies.

Unit 2 began commercial operations on May 19,1989 and has completed the first three cycles with the following average burnups:

Cycle 1 Completed 09/14/90 17,161 MWD /MTU Cycle 2 Completed 03/09/92 17,008 MWD /MTU Cycle 3 Completed 09/08/93 18,814 MWD /MTU One Hundred Fifty Seven of the 193 assemblics comprising Cycle 4 are based upon the VANTAGE 5 design.

2.0 UNIT 2 CYCLE 4 CORE REFUELING REFERENCES Westinghouse WCAP-13799, The Nuclear Desien Reoort for the Voctle Electric Generatine Plant. Unit 2. Cvele 4

SUMMARY

The offload of the Cycle 3 core commenced on September 20,1993 and was completed on September 24,1993. Core reload commenced on October 2,1993 and was completed on October 5,1993. The as-loaded Cycle 4 core is shown in Figures 1 through 5 which give the location of each fuel assembly and insert. The Cycle 4 core has a nominal design lifetime of 20,200 MWD /MTU and consists of 8 Region 3,28 Region 4A,48 Region SA,28 Region SB,49 Region 6A, and 32 Region 6B assemblies. Fuel assembly inserts consist of 53 full length control rods, two secondary sources, and 138 thimbic plugs. Assemblies in Regions 6A and 6B have a total of 8064 Integral Fuel Burnable Absorber rods, the pellets of which are coated for a total length of 129 inches and offset upwards 1.5 inches from the center of the fuel stack 3

m

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~3.0 CONTROL ROD DROP TIME MEASUREMFET i

PURPOSE The purpose of this test was to measure the drop time of all control rods under hot, full I

flow conditions in the reactor coolant system to ensure compliance with Technical Specification 3.1.3.4 requirements.

SUMMARY

OF RESULTS For the hot, full flow conditions (Tavg > 5510F and all reactor coolant pumps operating), Technical Specification 3.1.3.4 requires that the rod drop time from the fully withdrawn position shall be 5 2.7 seconds from the beginning of stationary gripper coil voltage decay until dash pot entry. All rod drop times were measured to be less than 2.7.

j seconds. ' The mean drop time was determined to be 1.605 seconds. The rod drop time results for dash pot entry are presented in Table 1.

j 4.0 INITIAL CRITICALITY PURPOSE The purpose of this test was to achieve initial reactor criticality under carefully controlled conditions, establish the power range for performance oflow power physics testing, and j

operationally verify the calibration of the reactivity conputer.

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SUMMARY

OF RESULTS q

i Initial reactor criticality for Unit 2 Cycle 4 was achieved, by dilution, at 0512 hours0.00593 days <br />0.142 hours <br />8.465608e-4 weeks <br />1.94816e-4 months <br /> on -

October 18,1993. The reactor was stabilized at the following critical conditions: RCS temperature 557 0F, Intermediate Range power of approximately 1 x 104 Amps, RCS boron concentration of 1864 ppm, and Control Bank D at 186 steps. Following j

stabilization, the point of adding nuclear heat was determined and a checkout of the reactivity computer was successfully accomplished. In addition, Source and Intermediate Range Nuclear Instrumentation overlap data were taken during the flux increase i

preceding initial criticality to demonstrate that adequate overlap existed.

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5.0 ALL RODS OUT ISOTIIERMAL TEMPERATURE COEFFICIENT ANT BORON ENDPOINT MEASUREMENT PURPOSE The objectives of these measurements were to determine the hot, zero power isothermal and moderator temperature coemeients for the all rods out (ARO) configuration and to measure the boron endpoint concentration.

SUMMARY

OF RESULTS The isothermal temperature coemcient was measured to be + 3.14 pcm/0F which met the design acceptance criteria of being within 2 pcm/0F of+ 2.69 pcmRF. This gave a calculated moderator temperature coemeient of + 5.21 penV0F which included a Doppler coemcient of-1.57 pcmPF and a burnup dependent correction factor of 0.5 pcmPF and was within the Technical Specification limit of + 7.0 pcm/ OF. Therefore no rod withdrawal limits were required to be established.

The measured ARO critical boron concentration of I878 ppm was within the design review criterion ofi 50 ppm of the design value of I852 ppm.

6.0 CONTROL AND SHUTDOWN BANK WORTH MEASUREMENTS Pb1 POSE The objective of the bank worth measurements was to determine the integral worth of each control and shutdown bank for comparison with design values.

SUMMARY

OF RESULTS The rod worth measurements were performed using the bank interchange (rod swap) method in which the wonh of the bank having the highest design worth (the Reference Bank) is measured using the standard boron dilution method and the rema' ming control and shutdown banks worth's are derived fmm the reference bank reactivity needed to offset full insertion of the bank under test. The control and shutdown bank worth measurement results are given in Table 2.

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7.0 STARTUP AND POWER ASCENSION PURPOSE The purpose of the power ascension program was to provide direction for Intermediate and Power Range detector calibration prior to startup and as needed during power ascension and to perform measurements and provide calibration data for incore-excore detector axial flux diffemnce, core hot channel factor, Reactor Coolant System 5f, and Reactor Coolant System flow at specified power level plateaus.

SUMMARY

OF RESULTS Full core flux maps were obtained at 33.4%,47.4%,74.4% and 99.8% power. Hot channel factors were evaluated at each power plateau end the resuhs are shown on Table

3. Reactor Coolant Flow was determined from pnicision calorimetric measurements at 92.5% power. Calibration constants for DELTA-T were determined at 74.4% power.

8.0 REACTOR COOLANT SYSTEM FLOW MEASUREMENT PURPOSE i

The purpose of this test was to determine the flow rate in each reactor coolant loop to confirm that the total flow met the minimum flow requirement given in Technical Specification 3.2.5.

SUMMARY

OF RESULTS The total flow was determined to be 397,872.8 gpm which is > the Technical Specification minimum limit of 384,509 gpm.

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TABLE 1 CONTROL ROD DASH POT ENTRY TIMES CONTROL DASII POT CONTROL DASIl POT ROD ENTRY ROD ENTRY LOCATION TIME (mses)

LOCATION TIME (msec)

D02 1684 M08 1588 B12 1616 1106 1574 M14 1686 1110 1618 PO4 1632 F08 1592 B04 1648 K08 1600 D14 1632 F02 1578 P12 1590 B10 1598 M02 1618 K14 1558 G03 1592 P06 1596 C09 1M4 B06 1644 J13 1604 F14 1612 N07 1552 P10 1612 C07 1586 K02 1568 G13 1624 1I02 1564 N09 1598 B08 1584 303 1608 Ill4 1564 E03 1560 P08 1572 Cll 1576 F06 1694 L13 1642 F10 1554 N05 1580 K10 1566 C05 1604 K05 1718 E13 1636 D04 1552 N11 1638 M12 1600 LO3 1618 D12 1600 i

1104 1544 MM 1602 D08 1630 1108 1612 Ill2 1618 Sample Size = 53 Mean = 1.605 seconds 2 Sigma Limits = 1.530 and 1.681 seconds Control rods D02, M14, F06, and K06 fell outside the 2 Sigma limits and were dropped an additional six times. The drop times for the extra drops were measured to be between 1.544 and 1.690 seconds. These Drop Times were consistent with the drop times of the other rods.

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TABLE 2

SUMMARY

' OF CONTROL AND SHUTDOWN ROD BANK WORTH MEASUREMENTS PREDICTED INTEGRAL MEASURED BANK WORTII AND BANK REVIEW CRITERIA WORTII PERCENT BANK focm)

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DIFFERENCE Control A 366 1 100 328.8

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Control B 645 1100 617.6

- 4.2 3.0 Control C 764 115 741.1 Control D 588 100 563.6

- 4.1 Shutdown A 264 100 265.0

+ 0.4 Shutdown B 809 1 81 778.5

- 3.8 (Reference)

Shutdown C 439 100 426.5

- 2.8 Shutdown D 439 1 100 426.2

- 2.9 Shutdown E 371 100 345.8

- 6.8 All Banks 4685 + 469 4493.1

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4 TABLE 3 i

SUMMARY

OF POWER ASCENSION FLUX MAP DATA Parameter Map 92 Mao 93 Mao 95 Map 96 t

Average % Power 33.4 47.4 74.4 99.8 f

LOPAR FN31{ Limit 1.821 1.772 1.647 -

1.529 LOPAR FN Measumd 0.7833 0.7974 0.7884 0.7724 311 N

VANTAGE 5F jil Limit 1.980 1.910 1.776 1.651 VANTAGE 5 FN Measumd 1.5611 1.5760 1.5538 1.5489 311 Transient FQ Limit 4.0412 4.0411-2.7742 1.8826 Most Limiting F (Z) + 2%

2.2446 2.0898 2.0248 1.8494 Q

Com Average AFD (%)

2.6 1.6

-1.3

- 2.9 Com Average Axial Offset (%)

7.864 3.424

-1.700

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