ML20117B715
| ML20117B715 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/15/1996 |
| From: | Colussy K, Dulick A, Zupsic G DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20117B700 | List: |
| References | |
| NUDOCS 9608270157 | |
| Download: ML20117B715 (12) | |
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DUQUESNE LIGHT COMPANY '
BEAVER VALLEY POWER STATION UNIT 1 -
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i CYCLE 12 STARTUP PHYSICS TEST REPORT l
l Prepared by: u t7 Reviewed by: /
K. A. Colu(ff G. F. p psic Reactor Engineer Supe Wisor, Reactor Engineering Reviewed by: '
Approved by: 2
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A. M. bulick' B. T. Tuite Manager, General Manager, Operations Experience Nuclear Operations
!l 9608270157 960815 <
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BEAVER VALLEY POWER STATION Cycle-12 Startup Test Report i
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INTRODUCTION:
Beaver Valley Unit 1 was shutdown on March 22, 1996, for its eleventh refueling outage. During the outage, 64 of 157 fuel assemblies were replaced with a split batch of 12 fuel assemblies of 3.62 w/o enrichment, 40 fuel assemblies of 3.60 w/o enrichment and 12 -
assemblies of 4.00 w/o enrichment. The fresh fuel rods are based on the Westinghouse Vantage 5 Hybrid (V5H)' design which is -characterized l by. the use of zircaloy grids with natural uranium in the top and bottom six inches of each fuel rod. Many of the fuel pellets.within- ]
the fuel rods of the fresh fuel assemblies have a coating of zirconium '
diboride (a neutron absorber). Rods with this coating are known as Integral Fuel Burnable Absorber (IFBA) rods and are used for power
~ j shaping and to reduce the initial critical boron concentration. I This report describes the startup test program applicable for the Cycle 12 reload core design verification for Beaver Valley, Unit 1.
This testing-program consisted of the following measurements conducted from May 8, 1996, through May 21, 1996:
- 1. Control rod drop time
- 2. Initial criticality
- 3. Boron endpoints
- 4. Temperature coefficient
- 5. Control bank worths
- 6. Reactimeter checks
- 7. 30% power symmetry check !
- 8. Incore versus Excore cross-calibration l
- 9. Power distribution measurements at 71% and 100% reactor i power.
The results of these startup tests are summarized in this report and i' comparisons are made to predicted design values and applicable Beaver Valley technical specification requirements. l i
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4 Beaver Valley Power Station Cycle 12 Startup Test Report TEST SU$MARIES:
1BVT 1.1.1, " Control Rod Drop Time Measurements" PURPOSE:
The purpose of this test is to determine a drop time for each full-length rod cluster control assembly (RCCA) with the reactor coolant system (RCS) in hot standby, Tavg > 541 F, and full RCS flow.
TEST DESCRIPTION:
A single RCCA bank is withdrawn to the full-out position (231 steps).
A recorder is connected to the analog rod position indication system primary coil of each control rod in the bank and one stationary gripper coil. The reactor trip breakers are opened and the drop trace for each rod in the bank is obtained from the recorder. Each of the 48 rod cluster assemblies are tested in this manner. The drop time is determined from the start of stationary gripper voltage decay to dashpot entry on the recorder trace.
RESULTS:
The test commenced at 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br /> on May 8, 1996, and was completed at 1243 hours0.0144 days <br />0.345 hours <br />0.00206 weeks <br />4.729615e-4 months <br /> on May 9, 1996. The drop times of the 48 rods were well ,
within the BVPS Unit 1 Technical Specification 3.1.3.4 requirement of '
< 2.7 seconds to dashpot entry. Figure 1 shows the drop times for each rod. The slowest drop time to dashpot entry was 1.35 seconds for god B-6 while the fastest drop time was 1.18 seconds for rods G-9 and K-12.
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Beaver Valley Power Station Cycle 12 Startup Test Report 1RST-2.1, " Initial Approach to Criticality After Refueling" PURPOSE:
The purpose of this test is 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 for criticality were established on May 10, 1996, at 0816 hours0.00944 days <br />0.227 hours <br />0.00135 weeks <br />3.10488e-4 months <br /> with shutdown banks fully withdrawn, control banks fully inserted, RCS boron concentration at 1474 ppm, RCS temperature at 547.8*F and RCS pressure at 2238 psig.
The control banks were withdrawn in normal sequence while pausing periodically to monitor inverse count rate ratio (ICRR). At 1028 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91154e-4 months <br />, criticality was achieved with Control Bank D at 200 steps.
Following the recording of criticality data, flux was increased toward nuclear heat. Nuclear heat was observed at 4.7 x 10-7 amps as indicated on the reactimeter. This corresponds to approximately 1.3 x 10-6 amps on Intermediate Range Detectors N35 and N36.
A reactimeter operational checkout was then performed using the reactor with positive reactivity insertions of 33 pcm and 26 pcm as indicated by the reactimeter. Calculated reactivity and theoretical reactivity were compared for the measured doubling time corresponding to each reactivity insertion.
1RST-2.1, " Initial Approach to Criticality After Refueling", was completed at 1356 hours0.0157 days <br />0.377 hours <br />0.00224 weeks <br />5.15958e-4 months <br /> on May 10, 1996.
RESULTS:
The all rods out (ARO) critical boron concentration corrected for rod position was calculated to be 1487 ppm which was within the acceptance criteria range of 1434 to 1534 ppm.
The LPPTB was set at 8.39 x 10-9 am to 1.5 x 10-7 amps based on 'a nuclear heating point of 4.7 x 10-gs amps and a background current reading of 8.39 x 10-10 amps for Power Range Detector N44.
The measured errors for the reactimeter checkout were -2.1% and -1.0%,
which were within the acceptance criteria of + 4%.
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Beaver Valley Power Station Cycle 12 Startup Test Report 1RST-2.2, " Core Design Check Test" PURPOSE:
The purpose of this test is to verify the reactor core design from hot-zero power (HZP) to 100 percent reactor power, and to perform the initial incore versus excore cross-calibration.
TEST DESCRIPTION:
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, e isothermal temperature coefficient, e differential boron worth, o boron dilution worth of the reference bank, control bank B (CBB),
e and rod swap bank worths.
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 prior to exceeding 75% reactor power to ensure the measured peaking factors were within their applicable technical specification limits.
Section D required an incore versus excore calibration between 45% and 90% of rated thermal power. This involved performing procedure IRST-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 adjustment.
Finally, Section E involved performing a full-core flux map at 100%
reactor power. This map served as a calibration check for the incore versus excore calibration and verified that the power distribution limits of the technical specifications are not exceeded. l I
RESULTS:
Doron Endpoint:
The all rods out (ARO) critical boron concentration was measured to be 1480.5 ppm, which was within the acceptance criteria of 1434 to 1534 ppm.
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Beaver Valley Power Station Cycle 12 Startup Test Report RESULTS: (Continued)
Bo'ron Enckpoint: (Continued)
The reference control bank B-in (CBB-in) critical boron concentration difference was measured to be 153.7 ppm, which was within the acceptance criteria of 142.2 to 173.8 ppm.
Temperature Coefficient:
The_ average ARO, HZP isothermal temperature coefficient (ITC) was determined to be -3.71 pcm/*F which was within the acceptance criteria of -2.53 to -6.53 pcm/ F.
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! The difference between the measured ITC and the predicted design value of the doppler coefficient (-1.74 pcm/ F)- equals the moderator temperature coefficient (MTC). The MTC was calculated to be -1.97 l_ pcm/ F. This value meets the requirements of BVPS Unit 1 Technical l
Specification 3.1.1.4 which requires the MTC to be between -50 pcm/ F j and 0 pcm/ F. -
l Differential Boron Worth:
The measured differential boron worth was 7.70 pcm/ ppm. This value was within the acceptance criteria of 6.58 to 8.90 pcm/ ppm.
Rod Cluster Control Assembly Bank Worths: ,
The boron dilution method of control rod worth measurement was used to l
[ determine the worth of control bank B (CBB). Due to a test equipment !
l problem, the reference bank for rod swap, CBB, was remeasured. The measurement was performed by withdrawing the bank to compensate for a constant boron addition to the RCS. CBB was then used to determine !
the worths of the remaining control and shutdown banks-relative to CBB ]
using the rod swap methodology. The measured worth, predicted worth, '
percent difference for each control rod bank and total worth of all l control rod banks are listed in Table 1. Figures 2 and 3 provide a graphical representation of differential and integral rod worth, -
respectively, for CBB. The measured values were within the acceptance criteria for this test as listed in Table 1.
Reactimeter:
j The reactimeter was checked prior to low power physics testing (LPPT) using an internal doubling time test and using the reactor following initial criticality. The highest error was measured with the reactor j to be -2.1%. This was within the + 4% acceptance criteria, i
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1 Beaver Valley Power. Station Cycle 12 Startup-Test Report RESULTS; (Continued) ,
30 Percent Power Symmetry Check:
A full-core flux map was performed on May 13, 1996, at approximately 28% reactor power with Control Bank D at 180 steps withdrawn, to determine the initial flux distribution in the core. Table 2 lists the values of incore quadrant tilt and maximum deviation from i predicted assembly powers for this flux map. The measured values were within the acceptance criteria.
l 71 Percent Power Flux Map and Incore versus Excore Calibration:
On May 15 and 16, 1996, 1RST-2.3, " Nuclear Power Range Calibration",
was performed at approximately 71% power. One full-core and six '
1 quarter-core flux maps were obtained at various axial offsets - to obtain data for the calibration of the excore detectors and to verify !
core peaking factors. The results of the full-core flux map are shown l in Table 2. The measured peaking factors were within the acceptance ]
criteria.
100 Percent Power Flux Map: .
On May 21, 1996, a full-core flux map was performed at 100% power.
This map served as a check for the incore versus excore calibration and power distribution limits. The results of the map are listed in Table 2. This map demonstrated that the incore versus excore calibration performed at 71% power was satisfactory. Analysis of the power distribution limits showed that Fxy and F delta H were within their respective surveillance limits.
The 100% power flux map marked the completion of the startup physics test program for Beaver Valley Power Station, Unit 1, Cycle 12.
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Beaver Valley Power Station Cycle 12 Startup Test Report i
TABLE 1
. . j CONTROL ROD BANK WORTHS Measured Predicted Value Value Acceptance Bank (pcm) (pcm) Error Criteria 1
CBD 975.26 1091 -10.61% i 15% j CBC 812.43 848 -4.19% i 15%
CBB* 1183.69 1222 -3.14% i 10%
i CBA 365.24 420 -54.75 pcm i 100 pcm SBB 1033.75 1070 -3.39% i 15%
SBA 781.59 895 -12.67% i 15%
i Total Worth 5151.96 5546 -7.10% i 10% i i
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- Reference Baux for Rod Swap l
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Beaver Valley Power Station Cycle 12 Startup Test Report TABLE 2 FULL CORE FLUX MAPS MAP 1201 MAP 1202 MAP 1209 Acceptance Parameters 28% Power 71% Power 100% Power Criteria Quadrant 1.0122 1.0103 1.0062 < 1.02 for Tilt 28% map Maximum -7.2% -5.7% -4.9% + 10% for Deviation Predicted from Relative Predicted Power > .9 Assembly Powers Tech. Spec.:
F delta H N/A 1.5527 1.5377 < 1.7592 for 71%
< 1.6216 for 100%
Tech. Spec.:
Fxy N/A 1.6941 1.6656 < 1.9243 for 71%
< 1.8212 for 100%
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1 Beaver Valley Power Station Cycle 12 Startup Test Report FIGURE l Unit 1 Cycle 12 HFF Rod Drops R P N M L K J H G F E D C B A i
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1 1.23 1.20 1.22 l 1.75 1.72 1.78 l 1
1.20 1.20 3
1.74 1.70 1.22 1.22 1.20 1.22 4 1.78 1.76 1.72 1.81 1.20 1.20 5 3,73 3,73 1.22 1.20 1.20 1.22 1.22 1.21 1.35 6 1.80 1.82 1.74 1.78 1,74 1.71 1.95 1.20 1.20 1.20 1.20 7 1.70 1.71 1.73 1.69 ,
i 1.20 1.22 1.22 1.28 I g
1.69 1.75 1,70 1.87 1.20 1.24 1.18 1.20 9 ,
1.70 1.70 1.73 1.76 ;
1.2 i 1.20 1.22 1.22 1.22 1.20 1.28 10 1.74 1.70 1 74 1 74 1.71 1.76 1.81 1.22 1.20 gg 1.73 1.72 <
1.22 1.18 1,20 1.20 12 1.72 1.6s i.73 1.72 i.22 1.20 l
13 1.73 1.73 1.30 1.22 1.23 4 1.85 1 79 1.73 15 Average Drop Time = 1.22 sec.
Festest Drop Time = 1.18 sec.
Slowest Drop Time = 1.35 sec.
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X.xX Breeker " Opening" to deshoot entry sec.
X.XX Breeker " Opening
- to deshoot bottom sec.
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