ML20216J977
| ML20216J977 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/13/1998 |
| From: | Colussy K, Macdonald J, Zupsio G DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20216J954 | List: |
| References | |
| NUDOCS 9804220052 | |
| Download: ML20216J977 (12) | |
Text
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4 DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION UNIT 1 l
CYCLE 13 STARTUP PHYSICS TEST REPORT l
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'1 Prepared by:
. #A --
Reviewed by:
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K. A. Coltis'sy G. F. Z4si#
Reactor Engineer
- SupeMsor, l
Reactor Engineering A
hk Approved by:
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Reviewed by:
O J.' B. Macdonaldi B. T. Tuite Manager, System and General Manager, Performance Engineering Nuclear Operations l
9804220052 980413 PDR ADOCK 05000334 I
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BEAVER VALLEY POWER STATION Cycle 13 Startup Test Report l
INTRODUCTION:
i Beaver Valley Unit I was shutdown on September 28,1997, for its twelfth refueling outage. During the outage,64 of 157 fuel assemblies were replaced with a split batch of 40 fuel assemblies of 4.20 w/o enrichment and 24 fuel assemblies of 4.60 w/o enrichment. The fresh fuel rods are based on the Westinghouse Vantage + design which is characterized by the use of ZIRLO* grids, fuel rod cladding, guide and instmmentation thimbles and 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 shaping and to reduce the initial critical boron concentration.
This report describes the startup test program applicable for the Cycle 13 reload core design verification for Beaver Valley, Unit 1. This testing program consisted of the following measurements conducted from December 27,1997, through January 30,1998:
1.
Control rod drop time 2.
Initial criticality 3.
Boron endpoints 4.
Temperature coeflicient 5.
Control bank worths 6,
28% power symmetry check 7.
Incore versus Excore instrumentation cross-calibration 8.
Power distribution measurements at 72% 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 Beaver Valley technical specification requirements.
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l Beaver Valley Power Station Cycle 13 Startup Test Report TEST SUMMARIES:
IBVT 1.1.1. " Control Rod Droo 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.
l TEST DESCRIPTION:
A single RCCA bank is withdrawn to the full-out position (231 steps). A recorder is connected to the l
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.
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i RESULTS:
The test commenced at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> on December 27,1997, and was completed at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on December 28,1997. 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 1.40 seconds for rod B-6 while the fastest drop time was 1.21 seconds for rod J-7.
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Beaver Valley Power Station Cycle 13 Startup Test Report 1RST-2.1. " Initial Ayproach 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 January 20,1998, at 0255 hours0.00295 days <br />0.0708 hours <br />4.21627e-4 weeks <br />9.70275e-5 months <br /> with shutdown banks fully withdrawn, control banks fully inserted, reactor coolant system (RCS) boron concentration at i
1698 ppm, RCS temperature at 546.5 F and RCS pressure at 2236 psig.
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The control banks were withdrawn in normal sequence while pausing periodically to monitor inverse count rate ratio (ICRR). At 0553 hours0.0064 days <br />0.154 hours <br />9.143518e-4 weeks <br />2.104165e-4 months <br />, criticality was achieved with Control Bank D at 200 steps.
j Following the recordin of criticality data, flux was increased toward nuclear heat. Nuclear heat was observed at 4.12 x 10 amps as indicated on the reactimeter. This corresponds to approximately 9x10-7 and 8x10-7 amps on Intermediate Range Detectors N35 and N36, respectively.
J A reactimeter operational checkout was then performed using the reactor with two positive reactivity insertions of approximately 44 and 32 pcm as indicated by the reactimeter. Calculated reactivity and theoretical reactivity were compared for the measured doubling time corresponding to each reactivity insertion.
IRST-2.1, " Initial Approach to Criticality After Refueling", was completed at 0825 hours0.00955 days <br />0.229 hours <br />0.00136 weeks <br />3.139125e-4 months <br /> on January 20,1998.
RESULTS:
1 The all rods out (ARO) critical boron concentration corrected for rod position was calculated to be 1711.5 ppm which was within the acceptance criteria range of 1656 to 1756 ppm.
The LPPTB was set at 7.0 x 10-10 amps to 1.3 x 10-7 amps based on a nuclear heating point of 4.12 x 10-7 amps and a background current reading of 7.0 x 10-1I mps for Power Range Detector N44.
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The measured errors for the reactimeter were -0.03% and -0.61%, which were within the acceptance criteria ofi 4%.
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Beaver Valley Power Station i
Cycle 13 Startup Test Report 1RST-2.2. " Core Desian Check Test" PURPOSE:
l 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 instrumentation cross-calibration.
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l 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:
l boron endpoints, e
isothermal temperature coefficient, 1
e differential boron worth, e
boron dilution worth of the reference bank, shutdown bank B (SBB),
e and rod swap bank worths.
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Section B involved performing a full-core flux map prior to exceeding 30% reactor power to verify core symmetry and proper core loading.
1 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 instrumentation calibration between 45% r.nd 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 l
calibration and adjustment.
l Finally, Section E involved performing a full-core flux map near 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.
RESULTS:
Boron Endpoint:
The all rods out (ARO) critical boron concentration was measured to be 1721.2 ppm, which was within the acceptance criteria of 1656 to 1756 ppm.
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Beaver Valley Power Station Cycle 13 Startup Test Report RESNLTS: (Continued)
Boron Endpoint: (Continued)
The reference bank-in, boron concentration difference was calculated by subtracting the reference bank-in boron endpoint from the ARO boron endpoint. This resulted in a boron concentration difference of 171.6 ppm, which was within the acceptance criteria of 145.8 to 178.2 ppm.
Temperature Coefficient:
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The average ARO, HZP isothermal temperature coeflicient (ITC) was determined to be -2.00 pcm/ F l
which was within the acceptance criteria of-0.54 to -4.54 pcm/ F.
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The difference between the measured ITC (-2.00 pcm/ F) and the predicted design value of the doppler coeflicient (-1.81 pcm/ F) equals the moderator temperature coefficient (MTC).
The MTC was calculated to be -0.19 pcm/ F.
This value meets the requirements of DVPS Unit 1 Technical Specification 3.1.1.4 which requires the MTC to be between -50 pcm/ F and 0 pcm/ F.
Differential Boron Worth:
The measured differential boron worth was 6.82 pcm/ ppm. This value was within the acceptance criteria of 6.171 to 8.349 pcm/ ppm.
Rod Cluster Control Assembly Bank Worths:
The boron dilution method of control rod worth measurement was used to determine the worth of the 1
reference bank for rod swap, shutdown bank B (SBB). The worths of the remaining control and J
shutdown banks were obtained relative to SBB using the rod swap methodology. The measured worth, predicted worth, percent difference for each control rod bank and total worth of all control rod banks are listed in Table 1.
Figures 2 and 3 provide a graphical representation of differential and integral rod l
worth, respectively, for SBB. The measured values were within the acceptance criteria for this test as l
listed in Table 1.
i 28 Percent Power Symmetry Check:
' A full-core flux map was performed on January 23,1998, at approximately 28% reactor power with Control Bank D at 175 steps withdrawn, to determine the initial flux distribution in the core. Table 2 lists the values ofincore quadrant tilt and maximum deviation from predicted assembly powers for this flux map. The measured values were within the acceptance criteria.
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i Beaver Valley Power Station Cycle 13 Startup Test Report RESULTS: (Continued) l 72 Percent Power Flux Map and Incore versus Excore Calibration:
On January 25 and 26,1998,1RST-2.3, " Nuclear Power Range Calibration", was performed at l
approximately 72% power. One full-core and six 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 in Table 2. The measured peaking factors were within the acceptance criteria.
100 Percent Power Flux Map:
l On January 30,1998, a full-core flux map was performed at 100% power. This map served as a check l~
for the incore versus excore calibration and power distribution limits. The results of the map are listed in L
Table 2.
The map showed that the incore versus excore calibration performed at 72% 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 13.
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Beaver Valley Power Station Cycle 13 Startup Test Report TABLE 1 CONTROL ROD BANK WORTHS
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Measured Predicted j
Value Value Acceptance Bank (oem)
(oem)
Enor criteria j
Control Bank D 1053.54 1101
-4.31%
i 15 %
1 Control Bank C 965.23 990
-2.50%
15 %
Control Bank B 1127.33 1167
-3.40%
i 15 %
l Control Bank A 240.78 285
-44.22 pcm i 100 pcm i
Shutdown Bank B*
1170.90 1173
-0.18%
i10%
Shutdown Bank A 858.53 872
-1.54%
15 %
t Total Worth 5416.31 5588
-3.07%
i 10 %
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- Reference Bank for Rod Swap l
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Beaver Valley Power Station Cycle 13 Startup Test Report TABLE 2 FULL CORE FLUX hfAPS hfAP1301 hfAP1302 hiAP1309 Earameters 28% Power 72% Power 100% Power Acceptance Criteria Quadrant Tilt 1.0178
< 1.02 for 28% map hiaximum
+6.1%
10% for Predicted Deviation Relative Power >.9 from Predicted Assembly Powers Tech. Spec.:
F delta H 1.5523 1.5378
< 1.7540 for 72%
< 1.6233 for 100%
Tech. Spec.:
Fxy 1.6643 1.5816
< 1.8465 for 72%
< 1.7523 for 100%
Fxy (RTP) = 1.75 i
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Beaver Va!!ey Power Station Cycle 13 Startup Test Report FIGURE I Beaver Valley Unit 1 Rod Orop Times For Cycle ia 3OL R
P N
M L
K J
H G
F E
D C
B A
1 1.30 1.27 1.24 2
1.71 1.69 1.69 1.23 1.25 3
1.65 1.69 1.26 1.23 1.24 1.24 4
1.82 1.65 1.72 1.66 1.22 1.24 5
1.65 1.68 1.24 1.25 1.25 1.24 1.25 1.25 1.40 6
1.68 1.74 1.67 1.67 1.69 1,76 1.84 1.24 1.21 1.23 1.25 7
1.66 1.73 1.66 1.76 1.24 1.22 1.22 1.32 8
1.67 1.64 1.68 1.88 1.24 1.26 1.24 1.24 9
1.67 1.70 1,72 1.64 1.25 1.23 1.25 1.22 1.23 1.24 1.31 10 1.72 1.67 1.67 1.68 1.67 1.68 1.75 1.24 1.22 11 1.65 1.66 1.24 1.22 1.22 1.23 12 1.66 1.64 1.66 1.72 l
1.24 1.23 13 1.65 1.65 1.36 1.25 1.25 14 1.79 1.68 1.67 15 Average Time to Dashpot 1.249 j
Fasteet Time to Deshpot 1.21 Slowest Time to Deanpot 1.40 Average Time to Sonom 1.895 Fastest Time to Sonom 1.64 Slowest Twne to Bottom 1.88 x.xxx Stabonary gnpper voltage decay to dashpot entry sec. (Tech Spec. requirement) x.xxx Stabonary gnpper voltage decay to dashpot bottom - sec.
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