ML20064H371

Cycle 5 Startup Physics Test Rept

ML20064H371
Person / Time
Site:	Beaver Valley
Issue date:	03/09/1994
From:	Colussy K, Dulick A, Zupsic G DUQUESNE LIGHT CO.
To:
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ML20064H171	List: ML20064H169 ML20064H371
References
NUDOCS 9403170273
Download: ML20064H371 (13)

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DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION UNIT 2 CYCLE 5 STARTUP PHYSICS TEST REPORT Prepared by: . >- Reviewed by: .A-K. A. ~Colussy[/ G. F. Z/p/16 Reactor Engineer SuperviMr, Reactor Engineering I

Reviewed by: - /a Approved by: P M /

A. M.Nulick L.U6."Preel'End Manager, General Manager, Operations Experience Nuclear Operations I

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9403170273 940309 PDR ADOCK 05000412 P PDR

BEAVER VALLEY POWER STATION Unit 2. Cycle 5 Startuo Test Report l

INTRODUCTION:

l Beaver Valley Unit 2 was shutdown on September 17, 1993, for its fourth refueling outage. During the outage, 68 of 157 fuel assemblies were replaced with a split batch of 48 fuel assemblies of 3.60 w/o enrichment and 20 assemblies of 4.0 w/o enrichment. The fresh fuel rods are based on the Westinghouse Vantage 5 Hybrid (V5H) design which is characterized by the use of zircaloy grids with natural uranium in the top and bottom six inches. Assemblies with integral fuel burnable absorbers (IFBA) have arrangements of 48, 80 and 128 rods with boride-coated pellets in the central 120 inches. A region of unpoisoned fuel six inches in length is found between the I natural uranium and the boride-coated fuel in these IFBA fuel assemblies. Additionally, 12 vibration suppression assemblics have been inserted into the guide tubes of the fuel assemblies on the i

outer flats. These vibration suppression assemblies are intended to dampen any flow induced vibrations in their respective fuel I assemblies.

l l

This report describes the startup test program applicable for the  ;

Cycle 5 reload core design verification for BVPS, Unit 2. This l testing program consisted of the following measurements conducted l from November 24, 1993, through December 20, 1993: i

1. Control rod drop times l 2. Initial criticality

3. Boron endpoints

4. Temperature coefficient ,

5. Control bank worths 1

6. Reactimeter checks

7. 30% power symmetry check

8. Incore/Excore cross-calibration

9. Power distribution measurements at 74% and 100% reactor

power.

The results of these startup tests are summarized in this report and comparisons are made to predicted design values and applicable BVPS technical specification requirements.

1 PAGE 1 OF 12

Beaver-Valley Power Station

. Cycle 5 Startup Test Report TEST SUMMARIES:

2BVT 1.1.1, " Control Rod Dron Time Measurements" PURPOSE:

The purpose of this test was to determine a drop time for each full-length rod control cluster assembly.(RCCA) with the reactor coolant system (RCS) in hot standby, Tavg 2 541*F and full RCS flow. The test also verifies that the digital rod position indicators (DRPI) are within 12 steps of the group demand counters for each control rod.

TEST DESCRIPTION:

A single RCCA bank is withdrawn to the maximum full-out position (231 steps). At 24 step increments, rod position is recorded from the DRPI control board display and the safety parameter display system for comparison with the group step counter indication.

After rod withdrawal, stationary gripper coil voltage, a 120-volt 60 Hz timing trace, and the sum of the signals from the digital rod position indication data cabinets A and B detector / encoder cards are connected to a multichannel recorder. At the power control cabinets, the movable gripper and stationary gripper fuses are removed to initiate the rod. drop. Each of the 48 rod cluster assemblies is tested in this manner and the rod drop times are determined from the recorder traces.

RESULTS:

The test commenced at 0052 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> en November 24, 1993, and was completed at 0024 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on November 25, 1993. The drop times of all 48 rods were well within the BVPS Unit 2 Technical Specification 3.1.3.4 requirement of 5 2.7 seconds to dashpot entry. Figure 1 shows the rod drop times for each rod. The slowest' drop time was 1.475 seconds for rod B-6 while the fastest' drop time was 1.345 seconds for rod H-6.

PAGE 2 OF 12

Beaver Valley Power Station Cycle 5 Startup Test Report 2RST 2.1, " Initial Acoroach to Criticality After Refuelina" PURPOSE:

The purpose of this test was to: (1) achieve initial criticality; (2) determine the point at which nuclear heat occurs and establish the low power physics testing band (LPPTB) ; and (3) verify the proper calibration of the reactimeter.

TEST DESCRIPTION:

Initial conditions were established on December 5, 1993, at 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br /> with shutdown banks fully withdrawn, control banks fully inserted, boron concentration at 2015 ppm, RCS temperature at 547.8'F and RCS pressure at 2235 psig.

The control banks were sequentially withdrawn in 50 stop intervals until Control Bank D reached 160 steps. During control rod withdrawal, the inverse count rate ratio (ICRR) was monitored and decreased from 1.0 to 0.44.

The ICRR was renormalized to 1.0 and dilution to criticality started at 1742 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.62831e-4 months <br /> at a rate of approximately 54 gpm ($ 1000 pcm/hr).

During the dilution, ICRR data was obtained at 20 minute intervals and plotted versus boron concentration and makeup water added. At 0044 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> on December 6, 1993, after 19,012 gallons of primary grade water had been added, criticality was achieved by withdrawing Control Bank D to 176 steps.

Following the recording of criticality data, flux was increase toward nuclear heat. Nuclear heatingwasobservedat9.74x10g ampg on the reactimeter. 6 This corresponds to approximately 1.3 x 10" amps and 1.5 x 10- amps on Intermediate Range Detectors N35 and N36, respectively.

A reactimeter operational checkout was then performed using the reactor with positive reactivity insertions of 18 pcm, 36 pcm, and 55 pcm as indicated by the reactimeter. Calculated reactivity and theoretical reactivity were compared for the measured doubling time corresponding to each reactivity insertion.

2RST-2.1, " Initial Approach to Criticality After Refueling", was completed at 0519 hours0.00601 days <br />0.144 hours <br />8.581349e-4 weeks <br />1.974795e-4 months <br /> on December 6, 1993.

RESULTS:

The all rods out (ARO) critical boron concentration corrected for rod position was calculated to be 1480.3 ppm which was within the acceptance criteria of 1388 to 1488 ppm.

PAGE 3 OF 12

I Beaver Valley Power Station Cycle 5 Startup Test Report RESULT'S: (Continued)

Tho LPPTB was set at . 3.67 x 10-9 amps to 3.08 x 10-7 amps based on an observed nuclear heating point of x 10-7 amps and a bac) ground current reading of 3.67 x 10-1g.74emps for Power Range Detector N44.

The measured errors for the reactimeter calibration check were 2.2%,

2.5% and 3.7%, which were within the acceptance criteria of i 4%.

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PAGE 4 OF 12 h tr-e.4 w 7 + d + w _<a.---- - _ _ r- r- r - --

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Beaver Valley Power Station Cycle 5 Startup Test Report 2RST-2.2. " Core Desian Check Test"

).

PURPOSE:

The purpose of this test was to verify the reactor core design from hot zero power (HZP) to 100 percent reactor power, and to perform the initial incore/excore cross-calibration.

TEST DESCRIPTION:

4 The test was divided into five parts:

Section A covered low power physics testing. These tests are performed in the low power physics testing band at less than 5%

reactor power. They include the following measurements:

boron endpoints, isothermal temperature coefficient, differential boron worth, boron dilution worth of the reference bank, control bank B (CBB),

and rod swap bank worths.

Section B involved performing a ft .v. - ^'uv map prior to exceeding 30% reactor power to verify core symzon:v -

ycoper core loading.

Section C required a full-core flux map to be obtained prior to exceeding 75% reactor power to ensure the measured peaking factors were within their applicable technical specification limits.

Section D required an incore/excore calibration between 45% and 90%

reactor power. This involved performing 2RST-2.3, " Nuclear Power Range Calibration", in which a series of flux maps are performed at various axial offsets to provide data for nuclear power range calibration and adjostment.

Finally, Section E involved performing a full-core flux map at 100%

reactor power. This rap served as a calibration check for the incore/excore calibration and verified that the' power distribution limits of the technical specifications were not exceeded.

RESULTS:

Boron Endpoints:

The all rods out (ARO)-critical boron concentration was measured to be 1474.5 ppm, which was within the acceptance criteria of 1388 to 1488 ppm.

PAGE 5 OF 12

A Beaver Valley Power Station Cycle 5 Startup Test Report RESULT'S: (Continued)

The reference control bank B-in (CBB-in) critical boron concentration difference was measured to be 157.2 ppm which was within the acceptance criteria of 139 to 169 ppm.

Temperature Coefficient:

The average ARO, HZP isothermal temperature coefficient (ITC) was ietermined to be -3.89 pcm/*F which was within the acceptance criteria of -5.16 n 3 pcm/*F.

Subtracting out the predicted design value of theLdoppler coefficient

(-1.74 pcm/*F) from the measured ITC, the inferred moderator temperature coefficient (MTC) was calculated to be -2.15 pcm/*F.

This value meets the regn.irements of BVPS Unit 2 Technical Specification 3.1.1.4, which requ3res the MTC to be between -50 pcm/*F and 0 pcm/*F. In addition, the station has in place procedures to ensure that a negative MTC is maintained throughout Cycle 5 core life.

Differential Boron Worth:

The measured differential boron worth was 7.51 pcm/ ppm, which was within the acceptance criteria of 6.63 to 8.97 pcm/ ppm.

Control Rod Bank Worths:

The boron dilution method of control rod worth measurement was used to determine the worth of the reference bank for rod swap, CBB. The worths of the remaining control and shutdown banks were obtained relative to CBB. The measured worth, predicted worth, and error for each control rod bank and the total worth of all control rod banks are listed in Table 1. Figures 2 and 3 provide a crashical representation of the differential and integral rod worth, respectively, for CBB. All measured values were within the acceptance criteria for this test as listed in Table 1.

Reactimetgr:

The reactimeter was checked prior to low power physics testing (LPPT) and at the conclusion of LPPT using an internal doubling time test.

In addition, the reactimeter was checked using the reactor following initial criticality. In all cases, the reactimeter error was within i the 4% acceptance criteria, with the highest measured error being l 3.7%. l 1

PAGE 6 OF 12 l 4

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Beaver Valley Power Station  ;

Cycle 5 Startup Test Report  !

l RESULTS: (Continued) <

30 Percent Power Symmetrv 3 Lg_ch: c A full-core flux map was performed on December 10, 1993, at 1 approximately 29% reactor power with Control Bank D at 177 steps I withdrawn to determine the initial -flux distribution in the core.

Table 2 lists the values of incore quadrant tilt and the maximum deviation from predicted assembly powers for this flux map. All measured values were within the acceptance criteria for the test.  ;

i 74 Percent Power Flux Map and Incore/Excore Calibration: )

i on December 12 and 13, 1993, 2RST-2.3, " Nuclear Power Range  !

Calibration", was performed at approximately 74% reactor power. One j full-core and six quarter-core flux maps were obtained at various  !

axial offsets to calibrate the excore detectors and verify core l peaking factors. The results of the full-core flux map are provided in Table 2. All measured peaking factors were within their 1 applicable technical specification limits.

100 Percent Power Flux Man:

On December 20, 1993, a full-core flux map was obtained at 100%

reactor power. This map served as a check for the incore/excore I calibration and power distribution limits. The results of the map are listed in Table 2. The incore/excore calibration performed at 74% power was satisfactory. Analysis of the power distribution limits showed that Fxy and F delta H were within their respective surveillance limits.

The 100% flux map marked the completion of the startup physics test program for Beaver Valley Power Station, Unit 2, Cycle 5.

l PAGE 7 OF 12

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Beaver Valley Power Station Cycle 5 Startup Test Report TABLE 1 CONTROL ROD BANK WORTHS Measured Predicted Worth Worth Error Acceptance Bank (ocm) (Dem) (%) Criteria CBB* 1180.56 1205 - 2.03 i 10%

CBD 1093.57 1140 - 4.07 i 15%

CBC 859.96 897 - 4.13 1 15%

CBA 540.16 537 3.2 pcm i 100 pcm SBB 927.53 976 - 4.97 i 15%

SBA 896.02 921 - 2.71 15%

Total 5497.80 5676 - 3.14 i 10%

Worth-e

• Reference Bank for Rod Swap

.t 5

PAGE 8 OF 12 i

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Beaver Valley Power Station Cycle 5 Startup Test Report TABLE 2 FULL CORE FLUX MAP

SUMMARY

FM20501 FM20502 FM20509 Acceptance Parameters 29% Power 72% Power 100% Power Criteria Quadrant Tilt 1.0118 1.0080 1.0076 $ 1.02 for power above 50%

Maximum 5.7% 4.3% 3.4% i 10% for Deviation From Predicted Relative Predicted Power > .9 Assembly Powers F delta H N/A 1.4298 1.4089 Tech. Spec.:

< 1.6728 for.74%

< 1.5521 for 100%

Fxy N/A 1.5084 1.4976 . Tech. Spec.:

< 1.7582 for 74%

< 1.6715 for 100%

Fxy (RTP) = 1.67 i

PAGE 9 OF 12  ;

._ . .. ._. . _ . _. . __ . . _ . _ . . _ . _ - _ __ _ m Beaver' Valley Power Station Cycle 5 Startup Test Report FIGURE 1 Unit 2 Cycle 5 HFF Rod Drops RPNMLKJHG FEDCBA r

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Slowest Drop Time

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X.X X Breaker "Openmg* te enshoot entry - see.

X.X X Sreeker " Opening" to dashpet bottom see, i.

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PAGE 10 OF 12

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