ML20245C432
| ML20245C432 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 06/14/1989 |
| From: | Capstick R VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| BVY-89-51, NUDOCS 8906260179 | |
| Download: ML20245C432 (14) | |
Text
__ _ _
lVERMONT YANKEE NUCLEAR POWER CORPORATION
- Ferry Road, Brattleboro, VT 05301-7002
) ENGINEE IN OFFICE s
. June 14, 1989 g$g"[y ,9 BVY 89-51 (sob) 779-6711 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Mr. William T. Russell Regional Administrator
References:
(a) License No. DPR-28 (Docket No. 50-271)
(b) Vermont Yankee Technical Specification, Section 6.7.A.1
Subject:
Vermont Yankee Cycle 14 Start-Up Test Report
Dear Sir:
Enclosed please find the Cycle 14 Start-Up Test Report for Vermont Yankee which is submitted to you in accordance with the requirements of Reference (b).
We trust that you will find this information satisfactory; however, should you desire additional information, please contact us.
i Very truly yours, VERMONT YANKEE NUCL POWER CORPORATION ll Robert W. Capstick ,
Licensing Engineer l RWC/b11/0413w l
Enclosure cc: U.S. Nuclear Regulatory Commission )
Document Control Desk Washington, DC.20555 1
NRC Resident Inspector - VYNPS 8906260179 890614 DR ADOCK O
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STARTUP TEST REPORT VERMONT YANKEE CYCLE 14
Introduction:
Vermont Yankee Cycle 14 initial startup commenced on April 8, 1989 following an 8 week outage for refueling, maintenance related activities and fuel sipping.
The core loading for Cycle 14 consisted of:
96 P8x8R P8DPB289 reinserts from Cycle 12 136 P8x8R BP8DRB299 reinserts from Cycle 13 48 P8x8R BD324B non-irradiated assemblies 88 P8x8R BD326B non-irradiated assemblies An as loaded Cycle 14 core map is included as Figure I. Details of the Cycle 14 core loading are contained in the Yankee Atomic Electric Company document YAEC-1706, " Vermont Yankee Cycle 14 Core Performance Analysis, October, 1988".
An in-sequence critical was performed satisfactorily on March 2, 1989.
The shutdown margin was verified to be satisfactory based on the data collected from the in-sequence critical. Startup commenced April 7, 1989 and steady state full power conditions were reached April 14, 1989.
Control rod coupling verification was performed satisfactorily for all 89 control rods on Feb. 28, Mar. 1, and Mar. 2, 1989. Control rod scram testing was performed satisfactorily prior to reaching 30% power per Tech.
Specs, for all 89 control rods on March 28 and April 10, 1989.
The final as loaded core loading was verified correct by Vermont Yankee and Yankee Atomic Electric personnel on Feb. 28, 1989.
Core Verification:
The final core loading was verified correct on Feb. 28, 1989. Three separate criteria were checked:
- 1. Proper bundle orientation was verified by checking channel fastener orientation and assuring that fastener orientation agreed with that shown in Figure II.
- 2. Proper bundle seating was verified by following Vermont Yankee Procedure VYOP 1411.
- 3. Proper core loading was verified by checking the serial number of each bundle through the use of a video camera. This verification was recorded on video tape and was later independently reviewed and reverified to agree with the licensed core loading of Figure I.
4
Process Computer Data Checks:
Process computer data shuffling checks were completed April 5, 1989.
These checks included various manual and computer checks of the new data constants. A check for consistency of the data was also performed by Yankee Atomic Electric Company and found to be satisfactory.
In-Sequence Critical:
Sequence 14-A-2 was used to perform the in-sequence critical test.
On March 2, 1989 control rods were withdrawn in-sequence until criticality was attained. Criticality was achieved on the 7th rod in group 2 (26-31) at notch position 20. The moderator temperature was 84.0 *F.
The actual critical rod pattern and the YAEC prediction agreed within
+/- 1%AK/K. Figure III shows the actual, predicted and the +/- 1% AK/K critical rod patterns.
Shutdewn Margin Testing The shutdown margin calculation was performed using data collected during the in-sequence critical and information provided in the Core Management Report. The required shutdown margin to be demonstrated was 0.32% 6K/K. The actual shutdown margin was shown to be 1.036% AK/K.
Rod Scram Testing:
Scram testing of all 89 control rods was completed on April 10, 1989.
All insertion times were within the limits defined in the Vermont Yankee Technical Specifications. Results of the testing are presented in Table IA.
In accordance with Technical Specifications Section 4.3.C.2, scram time information available for scrams occurring since the transmittal of the previous startup test report is also included in Table IB. All insertion times were within the limits defined in the Vermont Yankee Technical Specifications.
All scram time information was evaluated to ensure that proper drive performance is being maintained. No degradation of drive performance is noticeable.
, Thermal Hydraulic Limits and Power Distribution:
Core Maximum Fraction of Critical Power (CMFCP), Core Maximum Fraction of Limiting Power Density (CMFLPD), Maximum Average Planar Linear Heat Generation Rate ratio to its limit (MAPRAT) and the ratio of CMFLPD to the Fraction of Rated Power (CMFLPD/FRP) were all checked daily during the startup using the process computer. All checks of core thermal limits were within the limits specified in Technical Specifications.
The process computer power distribution was updated nine (9) times using the TIP system during the ascent to full power. The results of these updates are presented in Table II.
The LPRMs were calibrated once in conjunction with TIP set 1252. The initial checkout of LPRM high and low trip alarm setpoints was done at 0%
power on Mar. 30, 1989. The TIPS and the LPRMs were both functionally tested and found to operate satisfactorily.
The process computer power distribution update performed April 19, 1989 (TIP 1261) was used as a basis for comparison with an off line calculation performed using the Yankee Atomic Electric Company nodal code SIMULATE. For the power distribution of April 19, 1989 the SIMULATE core average axial power distribution was compared to that calculated by the plant process computer; comparisons are shown in Table III. A comparison was also performed between SIMULATE and process computer peak radial power; comparisons are shown in Table IV.
TIP Reproducibility and TIP Symmetry:
TIP system reproducibility was checked in conjunction with the power distribution update performed on April 10, 1989. All three TIP system traces were reproducible to within 2.4%.
The total TIP uncertainty was calculated using TIP 1261. Since the rod pattern was symmetric, the actual plant TIP readings were used in the calculation.
The resulting total TIP uncertainty for this case was 1.73 percent.
The results of the TIP uncertainty test as shown in Table V are well below the 8.7% acceptance criteria.
1
Figure I Cycle 14 Core Map VERMONY YANKEE 44 LYC l LYC LYC 8LYC LYCILYC 1491 161 177l178 1621150 42 LYC 3LYJl LYJ LYNJLYN LYJ ILYJ sLYC 205 065 1 105 8131 814 1061066 1206 ga MC iLYC b MC MJ , YJ 1 LYs MJitYJ MNI LYJ MJ ; MC MC 8 LYC 141 g153 229lI097 1091 817 0691070 8181110 098 1230 154 1142 38 LY 1(YJlLYJ LYNILYJ LYN! LYN LYJl M N LYJ l LW LYJ lLYJ LY 76420101 l041 LYN 765 001 lLYJ
-821 1 129 825l826 1301 822 002 1766 42 1102 [7643 36
[YC[Y YJ lLYN LYJ LYN YJlLYN LYJ lLYJ LYN 8 LYJ LYN LYJ LYNI LYJ 29l085 037 1769 005l773 0331 777 089 1090 7781 034 774 006 7701038 5YJit"Y 0861130
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LYT Dir:1Y3 Tfk i ttJ DR I IC ChT DtT TfJ TYi Lirf TYW TO MN 34 DP 193 ,013 l e l I MJIMC g 781 3113 785l017 7891 093 829 1 30 0941 790 018 l786 114l782 0141194 8
M YJ LYN 32 221YCjbNMC LY YNI LYC LYN LY LYNILYJ LYN 1 LY 793 073fLYN 7646l LYN797 ____
833
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_ _l 222 834 198 7981074 79447647 30 gI LYJf LYJ LYNjLYJ 0531 125 801 1057 LYN 841lLYJLYN LYJ LYNI LYN LYJ LYN LYN LYJlLYN LYJ LYJ fLYC 049 845 029' QM_8_5,0 MJ 01g_ l32g0581802 ' 126 l 054 WL 23 MC YJ LYJ L YJlLYN LYC LYN LYCl LYN LYCILYC YN 8 009 853 077l805 LYN MJ MN8 LYJ LYJ 165 081 157 857 1851861 1691170 862 LYCLYNlLYC 186 858_ ,1)g 101 QJf.,15i ,D12 qg2.lMLYC 26 LYNI LYN MClLYJ LYNI LYJ LYN ILYJ LYNs LYJ LYNI LYJ LYJ LYNLYJl LYN LYJl LYN LYJ 8 LYC 137 121 86) I 025g09I021 fitj,,,14 73l061 LYCILTN 877I B78 62 874 046 87LYN022 LYJl810026I 86 22 l138 24 LYJgLYN'i.YJ gLYN LYCgLYN YC g LYF LYClLYC YNi LYC MN8LY LYNILYJ 1331881 117 g 885 133 1 889 201g893 1811 897 LYNILYJ YN ILYC 2171218 898l182 8941202 8901134 8861118 882 1134 22 LYCILYN LYJi LYN LYJl LYN LYN LYCl LYN LYCILYC LYN LYC LYNI LYC 1
135 883 119I 887 135 0891 2031 LYNI LYJ LYNILYJ LYN lLYC LYCl895831 899 2191220 900 184 89u'204 892 3 136 888 1120 884 i136 20 LYC' LYJ LYNg LYJ LYNjLYJ LYNgLYJ YNl LYJ LYNILYN LYJ1 LYN LYJ1 LYN LYJ[ MN LYJILYN LYJ { U C 139 123 8671 027 811 8023 8711047 8751 063 879l880 0648 876 3
0488 872 0241812 0281868 124 1140 Ig LYCILYJ LYJl LYN LYJ LYN LYCl LYN LYCl U N LYClLYC LYNIM C LYNI LYC LYNILYJ LYNILYJ LYJtLYC 167108,3 011185p 0791 807 _1591859 871 863 171 1172 8641188 8603 16 8081080 8561012 ,4,3 168 16 LYC 1LYJl LYJ'LYli LYJ LYNILYJ LYN 1 LYJ LYN lLYN LYJILYN ,LYJl LY LYJaLYN 191 1055l 127 803 059 843l051 8471 031 851l852 0321848 0521 844 0601804 M J(LYJ YC 128 056 192 34 LY l LYN LYJ l MN LYCl LYN LYC LYN LYC LYC LYNILYC LYN 1 LYC LYNiLYJ LYNI LT 76481 79 075 1 799 1991835 223,g839 211 212 840l224 8361 200 8001076 7968 7645 12 MC ,MJ U l MJ MN LYJ LYNgLYJ LYN LYN M JsLYN LYJg LY LYJ LYN LYJ e LYC 195l015 783l115 787lg019 7911095 , 831 ll832 ,096l792 0203 788 116e784 016I 196 10 LYCILYJ LYJl LYN LYJ LYN ' MJBLYN L1J l MJ _
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1311087 0391771 00!l775 351779 091 1092 7801036 LYN 7761 008 7721040 LYJg LYC_
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F8GURE II CORE 2LL LOADING.CONFIGURA TION
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CRIT 2 CAL ROD 0, U A ION COMPAR! SON BEGINNING OF CYCLE 14 43 b fb 39 kb hb b b 35 hb ,
h3 31 b d4 27 48 48 23 48 48 48 48 48 48 19
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/ kb 15 b 11 48 07 kb b 03
-1% AK/K Predicted Critical Pattern 02 06 10 14 18 22 26 30 34 38 42 02 06 10 14- 18 22 26 30 34. 33 42 08 43 48 48 kb 48 39 b b Ib '
08 08 3s 4fi 4b 46 48 31 48 20 48 08 08 08 27 48 48 kb 48 48 48 23 48 48 48 48 48 48 08 -
08 08 19 48 48 4E 48 ,_ 1s 48 48 i 08 08 11 h$ kb !b I lb 07 kb kb 4b hb 08 03 41% AK/K Actual critical Pattern a Position 00 l
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TABLE IA CONTROL ROD SCRAM TESTING RESULTS VERMONT YANKEE BEGINNING OF CYCLE 14
' Single rod scrams - April 10, 1989 Mean time for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.341 0.862 1.391 2.522 Tech. Spec. limit (sec) 0.358 0.912 1.468 2.686 Maximum 87.84% insertion 'cime (sec) - 2.871 Tech. Spec. limit for slowest 87.84% insertion time (sec) - 7.000 Slowest 2x2 array for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.371 0.892 1.423 2.570 Tech. Spec. limit (sec) 0.379 0.967 1.556 2.848
TABLE IB CONTROL ROD SCRAM TIME RESULTS VERMONT YANKEE CYCLE 13 Full scram - October 3, 1967 Mean Time for % insertion 4.51% 25.34% 46.18% 87.84%
Meacured. time (sec) 0.299 0.834 1.379 2.535 Tech. Spec. limit 0.358 0.912 1.468 2.686 Maximum 87.84% imsertion time (sec) = 3.089 Tech. Spec. limit for slowest 87.84% insetion time (sec) = 7.000 Slowest 2x2 array for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.331 0.910 1.482 2.679 Tech. Spec. limit 0.379 0.967 1.556 2.848 Full scram - November 8, 1987 Mean Time for % insertion 4.51% 25.34% 46.18% 87.84%
__ __-~___-_____-_-______ _____ ___-__ ______ ___-__
Measured time (sec) 0.309 0.832 1.371 2.512 Tech. Spec. limit 0.358 0.912 1.468 2.686 Maximum 87.84% insertion time (sec) = 3.073 Tech. Spec. limit for slowest 87.84% insetion Eime (sec) = 7.000 Slowest 2x2 array for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.343 0.933 1.517 2.749 Tech. Spec. limit 0.379 0.967 1.556 3.848 Single rod scrams at power - April 30, 1988 Mean Time for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.318 0.837 1.367 2.497 Tech. Spec. limit 0.358 0.912 1.468 2.686 Maximum 87.84% imsertion time (sec) = 3.073 Tech. Spec. limit for slowest 87.84% insetion time (sec) = 7.000 Slowest 2x2 array for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (tec) 0.348 0.918 1.493 2.667 Tech. Spec. limit 0.379 0.967 1.556 2.848
TABLE fB (cont'd)
CONTROL ROD SCRAM TIME RESULTS VERMONT YANKEE CYCLE 13 Full' scram - June 18, 1988 Mean Time for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.274 0.778 1.286 2.377 Tech. Spec. limit 0.358 0.912 1.468 2.686 Maximum 87.84% imsertion time (sec) = 2.793 i Tech. Spec. limit for slowest 87.84% insetion time (sec) = 7.000 Slowest 2x2 array for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.286 0.819 1.348 2.493 Tech. Spec. limit 0.379 0.967 1.556 2.848 Full scram - June 24, 1988 Mean Time for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.273 0.773 1.279 2.370 Tech. Spec, limit 0.358 0.912 1.468 2.686 Maximum 87.84% imsertion time (sec) = 2.850 Tech. Spec. limit for slowest 87.84% insetion time (sec) = 7.000 Slowest 2x2 array for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.285 0.812 1.338 2.470 Tech. Spec. limit 0.379 0.967 1.556 2.848 Single rod scrams at power - October 29., 1988 Mean Time for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.309 0.819 1.335 2.445 Tech. Spec. limit 0.358 0.912 1.468 2.686 Maximum 87.84% imsertion time (sec) = 2.850 Tech. Spec. limit for slowest 87.84% insetion time (sec) = 7.000 1
Slowest 2x2 array for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.351 0.874 1.398 2.551 Tech. Spec. limit 0.379 0.967 1.556 2.848
TABLE II Power Distribution Measurements - Cycle 14 Start-Up April 7, 1989 - April 14, 1989 Date Power (%) Core Flow (%) CMFLPD* CMFCP* MAPRAT*
4/9/89 22.48 34.33 0.225 0.395 0.218 4/10/89 48.54 48.96 0.551 0.632 0.528 4/11/89 46.12 48.98 0.528 0.608 0.507 4/11/89 58.67 49.17 0.581 0.714 0.574 4/11/89 68.90 53.19 0.720 0.836 0.715 4/12/89 84.28 73.04 0.778 0.846 0.764 4/12/89 86.00 72.83 0.837 0.856 0.821 4/13/89 99.72 98.40 0.966 0.908 0.946 4/14/89 91.52 82.94 0.854 0. ? /1 0.841
- Tech. Spec Limit - 1.000 i
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I TABLE III l
Comparison of Process-Computer and SIMULATE
- Core Average Axial Power Distributions-Process SIMULATE-Node Computer PARTB 1
l 25 .1451 .0850 l 24 .3287 .3470 23 .4878- .4824 22 .6040 .5970 21 .7009 .7107-20 .8129 .8280' 19 .9723 .9677 18 1.0662 1.0792 17 1.1301 1.1712
(. 16 1.2371 1.2445 15 1.2864 1.2953 14 1.2665 1.3142 13 1.3048 1.3375 12 1.3475 1.3623 11 1.3448 1.3802 10 1.3319 1.3791' 9 1.3037 1.3425 8 1.2895 1.3189 7 1.2447 1.2914 6 1.2322 -1.2369 5 1.2082 1.1805 4 1.1250 1.1034 3 .9851 .9714 2 .7354 .7580 1 .4204 .2153
a TABLE IV comparison of 10 Highest Relative Radial Powers s
Location SIMULATE Plant ;
q 23-26 1.338 1.355 1 25_24 1.338 1.355 25_26 1.286 1.334 1
25-28 1.323 1.325 1
25-30 1.225 1.261-1 27-26 1.323 1.327 27-30 1.275 1.272 1
i 29-26 1.225 1.269 l
29-28 1.275 1.276 l 1
33-24 1.251 1.252 l
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TABLE V Total TIP Uncertainty TIP' Case Rod Pattern Power (%) Core Flow (%) Uncertainty (%)
1261 36 99.75 97.63 1.73 20 30 20 36 i
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