ML20044F967
| ML20044F967 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 05/18/1993 |
| From: | Helfenberger J COMMONWEALTH EDISON CO. |
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| References | |
| NUDOCS 9306010266 | |
| Download: ML20044F967 (19) | |
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i COMMONWEALTH EDISON COMPANY ZION GENERATING STATION i
4 DOCKET NO. 50-304 LICENSE NO. DPR-48 UNIT 2, CYCLE 13 STARTUP TEST REPORT 4
PREPARED BY:
John Helfenberger f
ZCORRTS-386 9306010266 930518 l
PEWt -ADOCK 05000304 p
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m..-
J TABLE OF CONTENTS SECllON E6GE I
Cover Sheet Table of Contents 1
1.0 INTRODUCTION
2
.i 2.0 UNIT 2. CYCLE 13 CORE CONFIGURATION 3
3.0 CONTROL ROD SYSTEM CHECKOUT 4
Table 3.2:
Hot Rod Drop Times 5
6 4.0 INITIAL CRITICALITY 7
1 5.0 ZERO P0HER PHYSICS TESTING 8
t 5.1 Boron Endpoint Measurements 9
5.2 Isothermal Temperature Coefficient Measurements 10 Table 5.1:
Isothermal Temperature Coefficient Measurements 5.3 Rod and Boron Worth Measurements 11 12 Table 5.2:
Rod Horth Measurements 13 i
6.0 AT POWER PHYSICS TESTING 14 6.1 Flux Map Power Distribution Measurements 15 Table 6.1.A:
Flux Map Characteristics 16 Table 6.1.B:
Flux Map Results 16 i
7.0 CONCLUSION
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8.0 REFERENCES
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1.0 JEIRQDUCTION Zion Unit 2, Cycle 12 completed operation on November 12, 1992 at 0132 hours0.00153 days <br />0.0367 hours <br />2.18254e-4 weeks <br />5.0226e-5 months <br />. _ The Cycle 12 burnup was 17,345 MHD/HTU, which was within the burnup window of 16,900 to 17,600 MHD/MTU for the Cycle 13 design i
assumptions.
The unit was in coastdc.n for the last two months of operation starting from approximately 15,562 MHD/MTV.
The Unit 2, Cycle 12 fuel was unloaded from December 4, 1992 through December 6,1992. Unit 2, Cycle 13 fuel was loaded from January 8, 1993 through January 12, 1993. The fuel was loaded as required for Cycle 13 operation.
The Unit 2, Cycle 13 fuel loading contained 84 fresh Vantage 5 fuel assemblies.
The features of the Vantage 5 design utilized in this core are listed as followed:
1)
Integral fuel Burnable Absorber (IFBA) 2)
Removable Top Nozzle (RTN) 3)
Debris Filter Bottom Nozzle (DFBN) 1 4)
Natural Enrichment Axial Blankets The remaining 109 assemblies in Cycle 13 are the OFA (Optimized Fuel Assembly) type used in the Zion cores since Unit 1. Cycle 8.
i Zero power physics testing was conducted from February 20, 1993 through February 21, 1993. The at-power physics testing was conducted from February 22, 1993 to March 10, 1993.
The results of the startup testing program are acceptable and verify the Westinghouse design of Cycle 13.
Commonwealth Edison, Nuclear Fuel Services (NFS) Department created the Nuclear Design Report (NDR) for Cycle 13 using Westinghouse core models. All applicable technical specification requirements have been met.
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.I 2.0 UNIT 2. CYCLE 13 CORE CONFIGUFlI1QH
]
The Unit 2,-Cycle 13 core configuration is illustrated in Figure 2.1.
The fresh fuel loading consists of 24 region 15A fresh assemblies, 28 region ISB fresh assemblies, and 32 region 15C fresh assemblies.
These fresh assemblies contain the following features:
1) 640 wet annular burnable absorber (HABA) rods.
2) 5648 fresh integral fuel burnable absorber (IFBA) rods.
In addition, burned fuel assemblies contain:
8 secondary source rods.
The two secondary source spiders, each containing four source rods, i
are positioned tn core locations H-3 and H-13.
The burnable absorber rods are used to maintain a negative moderator temperature-coefficient (MTC) at the beginning of life (BOL) and to f'atten the power distribution.
Listed below, in Table 2.1, is a summary of Cycle 12 to Cycle 13 assembly changes (Reference 1).
TABLE 2.1 Number of Assm.
Number of Assm.
E931R0 Enrichment fuel Tvoe in Cycle 12 in Cycle 13 12A 3.600 0FA 41 0
12B 3.398 0FA 12 0
13A 3.613 0FA 20 20 13B 3.208 0FA 44 13 14A 3.618 0FA 48 48 14B 3.424 0FA 28 28 15A Non-IFBA 3.3980*
V5 0
24 15A IFBA 3.3960*
V5 0
24 15B Non-IFBA 3.1977*
V5 0
28 ISB IFBA 3.2049' V5 0
28 15C Non-IFBA 3.6111*
VS 0
32 The location of the sources, HABA, and IFBA rods within the Cycle 13 core is shown in Figure 2.2, Reference 1.
These enrichments do not include the axial blankets which contain natural uranium. (w/o U-235 - 0.7419)
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3.0 00NTROL ROD SYSTEM CHECKOUT The control rod system was tested and verified to be operating properly prior to the Unit 2, Cycle 13 Startup.
Tests performed to verify proper operation included bank overlap and slave cycler i
checkouts as well as rod drop timings.
The bank overlap checkout proved the ability of the overlap uni t to step control rod banks in a predetermined sequence for a more u11 form reactivity insertion.
The slave cycler timings verified the proper sequencing of the control rod coil currents during the withdrawal and insertion sequences.
The coil current values agreed with the previous cycles' values.
The rod drop timings verified that under hot, full flow conditions, all rods will enter the dashpot region in less than 2.4 seconds after the loss of the stationary gripper voltage, as required by Technical Specifications (Tech Specs) 3.2.3.C.
All of the rod drops were performed from 231 steps.
The slowest rod, in core location P-8, dropped in 1.413 seconds.
The fastest rod, in core location P-12, dropped in 1.295 seconds.
The average of all rod drop times was 1.349 seconds. The rod drop times for locations where Vantage 5 assemblies were loaded, were consistent with rod drop times for all core locations.
Based on comparisons with data from previous cycle drop times, all drop times for Unit 2 Cycle 13 were acceptable.
Table 3.2 provides a summary of all.of the rod drop times for Cycle 13.
In addition to the above tests, the step counters, annunciators, rod bottom lights, and P/A converter were all observed for proper operation. Rod bank assignments were also verified by a visual check as required by Technical Specification 4.2.1.E.
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TABLE 3.2 UNIT 1. CYCLE 13 HOT ROD DROP TIMES t
t TIME FROM TIME FRW i
RCCA RCCA START TO DASHPOT START TO BOTTOM BANK CORE LOC.
(SECONDS)
(SECONDS)
SBA D-2 1.36 1.97 i
SBA B-12 1.33 1.92 SBA M-14 1.36 2.00 SBA P-4 1.32
.l.93 i
SBA B-4 1.33 1.91 SBA D-14 1.36 2.00
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SBA P-12 1.30 1.88
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SBA M-2 1.36 1.99 SBB G-3 1.34 1.93 SBB C-9 1.38 1.94 t
SBB-J-13 1.34 1.85 i
f SBB N-7 1.39 1.95 SBB C-7 1.37 1.97
-f SBB G-13 1.31 1.87 SBB N-9 1.37 1.97 SBB J-3 1.32 1.91 l
t SBC-E-3 1.34 2.00 l
f SBC C-11 1.37 1.93 SBC L-13 1.35 1.92 j
SBC N-5 1.35 1.93 SBD C-5 1.35 1.97 SBD E-13 1.35 1.94 SBD N-11 1 36 1.93 SBD L-3 1.36 2.02
~ ~ ~
j CBA H-6 1.36 1.88
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CBA H-10 1.36 1.92 CBA F-8 1.38 1.79 CBA K-8 1.32 1.99
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- Vantage 5 fuel assembly location I
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TABLE 3.2 (Continued)
UEIT 1. CYCLE 13 HOT ROD DROP TIMES TIME FROM TIME FROM RCCA RCCA START TO DASHPOT START TO BOTTOM e
c y_
CBB B-10 1.38 2.00 i
CB9 K-14 1.37 2.03 i
CBB P-6 1.36 1.95 l
CBB B-6 1.38 1.94 CBS F-14 1.37 1.97 CBB P-10 1.37 1.93
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l CBS K-2 1.36 1.97 CBC H-2 1.33 1.92 CBC B-8 1.35 1.96 CBC H-14 1.34 1.91 i
CBC P-8 1.41 1.97-p CBC F-6 1.33 1.89 i
CBC F-10 1.35 1.90 CBC K-10 1.34 1.86 l
CBC K-6 1.35 1.93 CBD D 1.33 1.89 CBD D-12 1.30 1.87 CBD M-12 1.34 1.91 CBD M-4 1.32 1.88 CBD H-4 1.32 1.93 CBD D-8 1.33 1.95 CBD H-12 1.36 1.92 CBD M-8 1.39 1.96 j
CBD H-8 1.34 1.97 l
Indicates Vantage 5 fuel assembly location.
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4.0 INITIAL CRITICAL 1:1 The initial control rod withdrawal began on February 19, 1993 at 2159 l
for Shutdown Bank A (SBA). Control tod withdrawal was stopped at 195 steps Control Bank D (CBD) with approximately 100 pcm rod worth remaining. An inverse count rate ratio (ICRR) was maintained throughout the rod withdrawal.
Dilution to criticality began on February 20, 1993 at 0004 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, with Control Bank D (CBD) at 195 steps and an initial boron concentration of approximately 1539 ppm. Unit 2 achieved criticality at 0422 hours0.00488 days <br />0.117 hours <br />6.977513e-4 weeks <br />1.60571e-4 months <br /> on February 20, 1993 with CBD at 188 steps and a boron concentration of approximately 1291 ppm. An ICRR plot was maintained as a function of primary water addition during the dilution to l
criticality.
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l 5.0 ZERO POWER PHYSICS TESTING-Zero Power Physics Testing was completed on February 21, 1993. All Technical Specifications and safety acceptance criteria _were met.
The zero power physics tests include:
1.
Boron Endpoint Measurements 2.
Isothermal Moderator Temperature Coefficient Measurements r
3.
Rod and Boron Worth Measurements 4.
Zero Power Flux Map Although the zero power flux map is part of Zero Power Physics Testing, it was determined to be deferrable at such a minimal flux l
level per ANSI Standard 19.6.1, Section 6.6.3 and was performed as part of At Power Physics Testing at 25.2% power as indicated by Core r
Delta Temperature.
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5.1 Boron Endpoint Measurements The purpose of this test was to determine the critical boron concentration for the following. rod configurations.
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All Rods Out (ARO), and 2.
Reference Bank In The reference bank is normally the bank with the highest predicted worth when inserted in an unrodded core.
Since Control Bank D (CBD) had the highest predicted worth, it was used as the reference bank.
The boron endpoint results were as follows:
Condit10D lieasurement (DSM Desion AccentanfJt Criteria _(ppm ARO 1305 1314 e 50 CBD in 1152 1154 e 21.8 CBD in neasured boron endpoint was well within the design ac:eptance criteria.
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5.2 Isothermal Temnerature coefficient Measurements The purpose of this test was to determine the Isothermal Temperature Coefficient (ITC) of reactivity for various reference bank positions within the temperature range of reactor startups.
The results of these measurements are shown below in Table 5.1.
The predicted values of ITC were more negative than the measured values, however, all measured values were within the design acceptance-criteria.
The Moderator Temperature Coefficient (MTC) was determined by accounting for the Doppler reactivity feedback. The value for MTC - ITC - Doppler Temperature Coefficient (DTC).
It was determined that the HTC could be positive under certain conditions of low temperature, and maximum. critical boron concentration.
Restrictions were placed upon the unit operation to insure that a negative MTC was maintained during operation.
This operating restriction is not necessary to meet Technical Specification Requirements.
TABLE 5.1 15014EBli&L TEMPERATURE COEFFICIENT MEASEEMEHIS Average Isothermal Temperature Coefficient Design Control Bank D Average Boron (pcm/F)
Acceptance Position Concentration Criteria (Steps'Hithdrawn)
(ppm)
Heasured Predicted *
(pcm/F) 212.0 1305
-3.02
-3.58
-3.58 e 2 18.0 1156
-5.59
-6.05
-6.05 s 2 Predictions from Reference 1. Tables 4, 5-1, and 7.2.
Predictions were based on critical boron concentrations of 13?)
ppm (ARO) and 1168 ppm (CBD in).
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5.3 Rod and Boron Worth Measurementi The purpose of this test was to determine the differential and integral worth of the reference bank over its entire travel in an-unrodded core and to determine the integral worth of the remaining banks using the rod exchange method.
Adequate shutdown margin is demonstrated based on the rod worth measurements meeting the required acceptance criteria.
i Rod worth measurements were performed under the guidance of the Westinghouse Rod Exchange topical report (Reference 3).
The document states that the allowable percent difference between measured and i
predicted worth is 10% for the reference bank,15% for individual rod banks, and 10% for the sum of all measured rod banks.
For individual banks with a predicted worth less than 600 pcm the allowable difference is 100 ptm rather than 15%.
The reference bank (CBD) worth was measured by boration and dilution.
The percent difference between the predicted worth and the measured worth by dilution and boration of CBD was determined to be 1.6% for the dilution, and 2.9% for the boration.
Both are well within the allowable limits of 101.
The results of the rod worth measurements are shown in Table 5.2.
The rod exchange technique required _ design calculations by NFS e
(Reference 2) to provide estimated critical positions of the reference bank after exchange with the bank being measured, hPx, and the associated correction factors, alpha x.
The measurements were obtained for three reference bank positions:
a)
Initially fully inserted position, (hMx) Initial b)
Critical position after exchange, hMx c)
Final fully inserted position, (hMx) Return The worth of a measured bank, WIx, is:
HIx - HMR - (delta rhol) x - (alpha x)(delta rho 2) x where:
WMR - The total measured worth of the reference bank.
(delta rhol) x - The reference bank worth from 0 steps to the average of (hMx) Initial and (hMx) Return (delta rho 2)x - The reference bank worth from hMx to 231 steps.
alpha x - A correction factor for the hMx worth due to the rodded geometry.
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5.3 Rod _and Boron North Measurements (Continued)
Using the rod exchange technique, all control and shutdown banks were er. changed with CBD.
The largest difference between a measured and i
predicted bank worth was 4.36% for Control Bank B.
The measured sum worth cf all banks, based on the dilution measurement of CBD, using the rod swap technique was 4886.25 pcm wisich differs by -1.46% from the predicted worth. All safety and design acceptance criteria are I
met.
The rod exchange method determines boron worth data from the boration and dilution of the reference bank.
The CBD inverse boron worth from dilution and boration, was measured to be -0.1171 ppm /pcm and
-0.1157 ppm /pcm respectively. The predicted value for inverse boron worth was -0.1187 ppm-pcm (Reference 1).
The difference between the measured and predicted inverse boron worth from dilution and boration was 1.35% and 2.531 respectively. There is no design acceptante criteria for inverse boron worth.
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TABLE 5.2 UNIT 2. CYCLE 13 ROD BANK HORTH Dilution Acceptance Predicted Dilution Worth Criteria Acceptance RCCA Horth Worth Difference Note 1 Criteria Bank (pcm)
(pcm)
(%)
(%)
Het CBD 1288.70 1309.50
-1.59 10.0 Yes CBC 869.50 849.59 2.34 15.0 Yes CBB 469.00 449.41 4.36 21.3 Yes CBA 448.20 441.02 1.63 22.3 Yes SBD 406.60 398.83 1.95 24.6 Yes SBC 406.60 392.83 3.51 24.6 Yes SBB 846.60 822.00 2.99 15.0 Yes SBA 223.40 223.08 0.15 44.8 Yes SUM 4958.68 4886.25 1.48 10.0 Yes Note 1:
For banks having a predicted integral worth equal to or less than 600 pcm, the absolute difference between the measured and predicted worth must be less than 100 pcm.
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r 6.0 AT POWER PHYSICS TESTING On February 22, 1993. Unit 2 was synchronized to the grid for_the j
start of (T.le 13. Full core flux maps were taken to support the
-l power ascension program.
The results of the at-power flux map measurements are summarized in i
the following sections. All safety and design acceptance criteria were met.
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4 6.1 Flux Hao Power Distribution Measurements Power distribution measurements were performed to support the power ascension and to fulfill the requirements of Technical Specifications 3.2.2.A.1 and 3.2.2.C.l.
The results of the flux maps are summarized in Tables 6.1.A and 6.1.B.
Table 6.1.A shows the reactor conditions at the time of each~
flux map and the quadrant power tilts for each map.
For all flux maps on Unit 2 Cycle 13.to date, the most limiting peaking factors were in Vantage 5 assembles.
Table 6.1.B shows the most limiting measured peaking factors and the peaking fsetor limits.
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TABLE 6.1.A FLUX HAP CHARACTERISTICS t
Map Power Level C80 Position Incore Axial Burnup Number Date
(%)
(Steps Withdrawn)
Offset (%)
(MWD /MTU) 2-i3-01 02-24-93 25.2 199 0.415 15.0
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2-13-02 02-28-93 69.6 231 1.848 89.7 2-13-03 03-01-93 70.0 231 2.929 120.0 2-13-04 03-01-93 70.1 231
-0.711 126.0 2-13-05 03-04-93 89.3 231
-2.932 198.0 t
2-13-06 04-05-93 99.1 221
-3.879 1332.0 2-13-07 04-05-93 98.8 211 0.441 1343.0 j
2-13-08 04-06-93 98.9 231 3.170 1360.0
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i 2-13-09 04-06-93 98.9 231
-7.422 1380.0 t
TABLE 6.1.B l
FLUX MAP _RES11LIS j
P
- Measured Peaking Peaking Factor
_l Factors Limits Incore Quadrant Tilts i
Map Number F-Delta H F-Q F-Delta H F-Q N-41 N-42 N-43 N-44 j
2-13-01 1.6851 2.2627 2.0203 4.8000 1.0015 0.0116 0.0136 0.9734 j
2-13-02 1.6477 2.0587 1.8004 3.3707 1.0032 1.0026 1.0104 0.9837 2-13-03 1.6539 2.0885 1.7985 3.3429 1.0031 1.0008 1.0103 0.9858 2-13-04 1.6501 2.1130 1.7981 3.4240 1.0025 1.0005 1.0100 0.9870 1
a 2-13-05 1.5700 2.0350 1.7030 2.6880 1.0076 0.9934 1.0106 0.9885 2-13-06 1.5490 2.0602 1.6540 2.4220 1.0113 0.9887 1.0111 0.9888
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2-13-07 1.5507 2.1698 1.6500 2.4300 1.0119 0.9880 1.0093 0.9908
?-13-08 1.5543 2.0491 1.6554 2.3964 1.0140 0.9874 1.0099 0.9888 2-13-09 1.5480 2.1290 1.6554 2.4267 1.0111 0.9890 1.0100 0.9900 Measured Peaking Factors include the required uncertainties.
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7.0 CQHCLUSIONS The Startup Testing Program was completed with satisfactory results.
All design acceptance criteria, safety acceptance criteria, and Technical Specifications were met.
The Startup Testing Program verified NFS' analyses for Unit 2, Cycle.13.
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'8.0 RELEREtCES 1.
NFSR-0099, " Zion Unit 2 Cycle 13 Nuclear Design _ Report",
February, 1993.
2.
Letter from NFS, 22C13/054, R.J. Chin to Mr. D.B. Wozniak,
" Zion 2,-Cycle 13 Rod Exchange Data", January 26, 1993.
1 3.
Ceco Letter J.S. Abel to H.R. Denton, "Use of Rod Exchange Technique for Rod Worth Measurements at Zion Station",
February 4, 1981.
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