ML20248A777
| ML20248A777 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/30/1989 |
| From: | Burter A DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20247M377 | List: |
| References | |
| NUDOCS 8908090027 | |
| Download: ML20248A777 (11) | |
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DUQUESNE LIGHT COMPANY DEAVER VAU2Y POWER STATION LTIT 2 CYCLE 2 STARTUP PHYSICS TEST REPORT June, 1989 f\
Prepared by: __ Itovlewed by: / -
M1At Ar
[C4 .
/ pi A. R. Burger T. G. Zyra Senior Engineer Terting and Plant Performance Director Reviewed by:
bl W/ ./
///(# Approved by:j
/ f i R. J. Druga T. P. Noonan Technical Services General Manager Manager Nuclear Operations 8908090027 890724 i PDR ADOCK 05000412 PDR U L _P_ _ __ _ _______
)
BEAVER VALLEY POWER STATION Unit 2. Cvele 2 Sgt.rtun Test Report INTRODUCTION:
Beaver Valley Unit 2 was shutdown on March 18, 1989 for its First Refueling Outage. During the outage, 56 of 157 fuel assemblies were replaced with a split batch: 20 fuel assemblies of 3.4 w/o enrichment and 36 fuel assemblies of 3.8 w/o enrichment. The fresh fuel rods are based on the standard design with natural uranium in the top and bottom six inches. Assemblies with Integral Fuel Burnable ;
Absorbers (IFBA) have arrangements of 32, 64, 80, and 160 rods with boride-coated pellets in the central 120 inches. A region of unpoisoned fuel six inches in 1 length is found between the natural uranium and the boride-coated fuel in these $
IFBA fuel assemblies.
This report describes the startup test program applicable for the Cycle 2 reload core design verification for BVPS, Unit 2. This testing program consisted of the following measurements conducted from May 13, 1989 through June 12, 1989:
- 1. Control rod drop times
- 2. Initial criticality )
- 3. Boron endpoints
- 4. Control bank worths j
- 5. Temperature coefficient {
- 6. Reactivity computer checks
- 7. 30% power symmetry check
- 8. Incore/Excore cross-calibration
- 9. Power distribution measurements at 73% and 100% reactor power )
- 10. Alignment of excore instrumentation for low-leakage fuel loading The results of these startup tests are summarized in this report and I
comparisons are made to predicted design values and applicable BVPS Technical Specification Requirements.
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. TEST SUMMARIES:
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l' 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 Cluster Assembly at. Hot Scandby and full RCS flow conditions. The test also verifies that the Digital Rod Position Indicators are within 12 steps of the.
group demand counters for each control rod.
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TEST DESCRIPTION:
A single RCCA Bank is withdrawn to the full-out position (228 steps). At each 24 step increment, rod position is recorded from the RPI contro1' board display and.
the Safety Parameter Display System for comparison with the group step counter indication.
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'After rod withdrawal, stationary gripper coil voltage, a 120 volt 60 Hz timing trace, and signals from the Digital Rod Position Indication Data Cabinets A:
and B detector / encoder cards are connected to a multichannel visicorder. 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 visicorder traces.
RESULTS:
-The test commenced at 1156 on May 13, 1989 and was completed at 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br /> on May 15,-1989. The drop times of all 48 rods were well within the BVPS Unit 2 Technical Specification Requirement of < 2.2 seconds, with the slowest time being 1.47 seconds for rod G-3 at hot full RCS flow.
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- l 3BVT 2.2.4."Alienment of Excore Instrumentation for Startun After Reload"
{ PURPOSE:
1 The purpose of this test wcs to adjust the Intermediate and Power Range Channel Reactor Trip Setpoints prior to startup due to a transition to a low leakage core loading pattern. This test also monitored actual plant power ascension data to determine whether any adjustments to these calculated setpoints were necessary.
TEST DESCRIPTION:
The Intermediate and Power Range Reactor Trip Setpoints were adjusted to the predicted assembly powers for the new core loading pattern. This was accomplished by ratioing Cycle l's measured assembly powers (based on incore flux mapping data) to the predicted assembly powers for Cycle 2. The Intermediate Range Detectors were expected to see approximately a 45% reduction in neutron flux while the Power Range Detectors were expected to see approximately a 40% reduction in neutron flux.
During power ascension, reactor power, delta T, and intermediate / power range detector overlap data were trended.
RESULTS:
Reactor power and Intermediate / Power lange Channel Reactor Trip Setpoints were adjusted based on design data prior to initial criticality for Cycle 2.
Following the completion of Low Power Physics Testing, reactor power was monitored and a calorimetric was performed prior to exceeding 30% reactor power. The calorimetric performed prior to 30% power indicated 24% while the power range channels read approximately 28.5%. The power range channels were adjusted to the measured data and power ascension continued.
All the reactor trip setpoints were more conservative than the allowable BVPS Unit 2 Technical Specifications during power ascension. No adjustments to the Intermediate and Power Range Channel Reactor Trip Setpoints were necessary.
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2BVT 2.2.1. " Initial Acoroach 'to Criticality After Refueline"
. PURPOSE:
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f 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); (3) verify the proper calibration of the reactivity
. computer.
. TEST-DESCRIPTION:
11nitial conditions were established on May 16, 1989 at 0116 with the ifo11 cuing' conditions; shutdown banks fully withdrawn, control banks fully-inserted, boron concentration at 1900 ppm, RCS temperature at 546 F,.and RCS pressure at 2230 psig.
The control ban'ks were' withdrawn in 50 step intervals until Control Bank D reached 160 steps. During control rod withdrawal, the Inverse Count Rate Ratio (ICRR) was monitored at 50 step increments and decreased from 1.0 to 0.45.
.The ICRR was renormalized to 1.0 and dilution to criticality started at 0400 at a rate of approximately 1000 pcm/hr. During the dilution, ICRR data was obtained at 20 minute intervals and plotted versus boron concentration and makeup water added. At 0828, on May 16,1989 after 16,376 gallons of primary makeup water had been injected criticality was achieved.
Following the recording of criticality data, flux was increased towards nuclear heat. Nuclear heating was observed at 6.6 x 10-7 amps on the reactivity computer.
A reactivity computer calibration check was then performed using the reactor with positive reactivity insertions of 21 pcm, 30 pcm, and 52 pcm. The doubling times were measured and predicted reactivity compared to measured for each l insertion.
2BVT :2.2.1'was completed at 1150 on May 16, 1989.
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RESULT 5:
The All Rods Out (ARO) critical boron concentration corrected for rod position was calculated to be 1471 ppm which was within the acceptance criteria of 1445 50 ppm.
The LPFTB was set at 2.7 x 10-9 amps to 3 x 10-8 amps based on an
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observed nuclear heating point of 6.6 x 10~7 amps and a background current reading of 2.7 x 10-10 amps for power range detector N44.
l The measured errors for the reactivity computer calibration check were 0.48%,
0%, and -2.8%, which was within the acceptance criteria of 4%.
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e 2BVT 2.2.2. " Core Desien Check Test" PURPOSE:
The purpose of this test was to verify the reactor core design from hot zero power to 100 percent reactor power, and to perform the initial incore/excore cross-calibration.
TEST DESCRIPTION:
The test was divided into five parts:
Section A covered Low Power Physics Testing. These tests are performed at less than 5% reactor power in the Low Power Physics Testing Band and include the following measurements: boron endpoints, boron dilution worth measurement of the reference bank (CBB), rod swap bank worths, differential boron worth, and an isothermal temperature coefficient measurement.
Section B involved performing a full-core flux map prior to exceeding 30%
reactor power to verify core symmetry and proper core loading.
Section C required a full-core flux map to be obtained between 40% and 75%
reactor power to ensure the measured peaking factors were within their applicable Technical Specification Limits.
Section D required that an incore/excore cross calibration be performed between 50% and 100% reactor power to calibrate the delta flux and delta-T circuitry of the power range detectors. 2BVT 2.2.3, " Nuclear Power Range Calibration", was performed to obtain a series of flux maps at various axial offsets to complete this section.
Finally, Section E involved performing a full-core flux map at 100% reactor power. This map served as a calibration check for the incore/excore calibration and verified that the power distribution limits of the Technical Specifications were not exceeded.
l RESULTS:
s Boron Endpoints:
I The All Rods Out (ARO) cricical boron concentration was measured to be 1455.5 i ppm which was within the acceptance criteria of 1445 i 50 ppm. l l
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- -The Control' Bank B-in critical boron concentration was measured to be 1323.5 ppm which was within'the acceptance criteria of 1304 ppm 15% (1108.4 ppm to l
.1499;6 ppm)'.
Tennerature Coefficient:
The' ARO, HZP Isothermal Temperature Coefficient (ITC) was determined to be
-2.30 pcm/F which was within the acceptance criteria of -2.95 3 pcm/F.
Subtracting out the predicted design value of'the Doppler Coefficient (-2.25 pcm/F) from the measured ITC, the inferred Moderator Temperature Coefficient (MTC) was calculated to be -0.05 pcm/F. This value meets'the requirements of the BVPS Unit 2 Technical Specifications which requires the MTC to be between -50 pcm/F and i 0 pcm/F. !
Differential Boron Worth:
The measured differential boron worth was 8.76 pcm/ ppm which was within the acceptance criteria of 8.47 pcm/ ppm 15% (7.20 pcm/ ppm to 9.74 pcm/ ppm).
RCC Bank Worths:
The boron dilution method of rod worth measurement was used to determine the worth of the-reference bank (Control Bank B) for rod swap. The worths of the remaining control and shutdown banks were obtained relative to CBB. The measured North, predicted value, and percent difference for each RCC bank and total RCC
.th are listed in Table 1. All the measured values were within the acceptance
' criteria'for this test.
Reactivity Computer:
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The reactivity computer calibration was checked prior to Low Power Physics Testing (LPPT) and every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the test using the exponential generator.
In addition, an operational calibration check using the reactor was also performed following initial criticality. In all cases the computer error was within the 4%
acceptance criteria, with the highest measured error being 2.8%.
30 Percent Power Symmetry Check: !
A full-core flux map was performed on June 4,1989 at approximately 30%
reactor power with Control Ban ~k D at 175 steps to determine the initial flux distribution in the core. Table 2 lists the values for quadrant tilt and maximum deviation from predicted assembly powers for the 30% flux map. All measured values were within the acceptance criteria.
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'73 Percent Power Flux Man and Incore/Excore Calibration:
On June 6 and' 7,1989 2BVT 2.2.3. " Nuclear Power Range Calibration" was D . performed at approximately 73% reactor power. This test involved a full-core and four quarter-core flux maps.obtained at various axial offsets to calibrate the
.excore detectors'and verify core peaking factors. The results of the full-core flux map are shown in Table 2. All the measured values were within the acceptance criteria for the applicable Unit 2 Technical Specifications.
I-100 Percent Power Flux Man:
On June .12,1989 a full-core flux map was performed at 100% reactor power.
This map served.as a check for the incore/excore calibration and power distribution limits. The results of the map'are shown in Table 2 All the measured.
peaking factor data was within the acceptance criteria and the incore/excore calibration performed at 73% power;was satisfactory.
The 100%' flux map marked the completion of the reload startup test program
=for Beaver Valley Power Station Unit 2, Cycle 2.
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l TABLE 1 CONTROL ROD BANK VORTHS Measured Predicted Worth Worth Error Acceptance Bank (ncm) (nem) (%) Criteria CBB* 1157.0 1194 -3.1 10%
CBD 1135.6 1157 -1.8 15%
CBC 956.1 945 1.2- 15%
CBA 458.0 459 -0.2 15%
SBB 962.3 969 -0.7 15%
SBA 1103.2 1141 -3.3 15%
Total Worth 5772.2 5865 -1.6 15%
- Reference Bank for Rod Swap.
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v TABLE 2 FULL CORE FLUX MAP
SUMMARY
30% Power 73% Power 100% Power CBD CBD CBD Acceptance l Parameters 175 stens 197 stens 228 stens _Qriteria Quadrant 1.0052 1.0052 1.0039 s 1.02 for power Tilt above 50%
Maximum Deviation 10% for from Predicted 4.4% -3.2% 3.6% Predicted Relat ve Assembly Powers Power > .9 Tech. Spec.:
F delta H N/A 1.4942 1.4854 < 1.6753 for 73%
< 1.5528 for 100%
Tech. Spec.:
i'xy N/A 1.6165 1.6081 < 1.7811 for 73%
< 1.6921 for 100%
Fxy(RTP) - 1,69 l
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