ML20063A418
| ML20063A418 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/13/1994 |
| From: | Tremblay L VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BVY-94-03, BVY-94-3, NUDOCS 9401260017 | |
| Download: ML20063A418 (14) | |
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VERMONT YANKEE NUCLEAR POWER CORPORATION e.
=4~ Ferry Road, Brattleboro, VT 05301-7002
[
ENGINE RING OFFICE M *'- 5dO MA!N S TRE ET DOLIOff MA 01740
[* (',00 : 779 6711 January 13,1994 BVY 94 - 03 United States Nuclear Regulatory Commission ATfN: Document ControlDesk Washington, DC 20555
References:
- a. License No. DPR-28 (Docket No. 50-271)
Subject:
Vermont Yankee Cycle 17 Start-Up Test Report
Dear Sir:
Enclosed please find the Cycle 17 Start-Up Test Report for Vermont Yankee, which is submitted to you in accordance with the requirements of Section 6.7.A.1 of the Vermont Yankee Technical Specifications.
We trust that you will find this information satisfactory; however, should you desire additional infonnation, please contact this office.
)
i Very truly yours, I j
VER,MONT YANKEE NUCLEAR POWER CORPORATION l
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Leonard A. Tremblay, Jr.
Senior Licensing Engineer ( ;
Enclosure l
cc: USNRC Region I Administrator USNRC Resident Inspector- VYNPS USNRC Project Manager- VYNPS j i
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9401260017 940113 n '
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I ADOCK 05000271 I I PDR
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STARTUP TEST REPORT VERMONT YANKEE CYCLE 17 i
l Introduction; Vermont Yankee Cycle 17 initial startup commenced on October 23,1993 i following a 58 day outage for refueling, maintenance activities and fuel sipping.
The core loading for Cycle 17 consists of:
52 BP8DWB311-10GZ reinserts from Cycle 15 60 BP8DWB311-11GZ reinserts from Cycle 15 40 BP8DWB311-10GZ reinserts from Cycle 16 88 BP8DWB311-11GZ reinserts from Cycle 16 96 BP8DWB335-10GZ non-Irradiated assemblies 32 BP8DWB335-11GZ non-Irradiated assemblies An as-loaded Cycle 17 core map is included as Figure 1. Details of the Cycle 17 core loading are contained in the Yankee Atomic Electric Company document YAEC-1867, " Vermont Yankee Cycle 17 Core Performance Analysis Report",
June,1993.
The final as-loaded core loading was verified correct by Vermont Yankee personnel on October 5,1993.
Control rod coupling verification was performed satisfactorily for all 89 control rods on 5, 6 and 16 October,1993. Control rod scram testing was performed satisfactorily prior to reaching 30% power per Technical Specifications. The testing was performed for all 89 control rods on 17 and 18 October,1993.
An in-sequence critical was performed satisfactorily on October 24,1993. The shutdown margin was verified to be satisfactory based upon the data collected from the in-sequence critical.
Startup commenced October 23,1993 and steady state full power conditions were reached October 28,1993.
l 1
l f Core Verification:
The final core loading was verified correct on October 5,1993 in accordance with Vermont Yan 3 procedure OP 1411. Three separate criteria were checked:
- 1. Proper bundle seating was verified.
- 2. Proper bundle orientation, channel fastener integrity and upper tie plate cleanliness were verified.
- 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 1.
1 Process Comouter Data Checks:
Process computer data shuffling checks were completed on October 18,1993.
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 (YAEC) and found to be satisfactory in-Secuence Critical:
The in-sequence critical test was performed on October 24,1993 as part of the reactor startup. Control Rod sequence 17-A-2(4 was used to perform the in-sequence critical test. Criticality was achieved on the 8th rod in group 2 (18-15) at notch position 26. The moderator temperature was 158'F.
The actual critical rod pattern and the prediction agreed within +/-1% Ak/k.
Figure li shows the actual, predicted and the +/-1 % Ak/k critical rod patterns.
Cold Shutdown Marain Testina:
The cold shutdown margin calculation was performed using data collected during the in-sequence critical and information provided in the YAEC " Core Management Report". The minimum shutdown margin required was 0.32% Ak/k.
The actual shutdown margin was shown to be 1.266% AK/K.
Control Rod Scram Testina:
Single rod scram testing of all 89 control rods was completed on 17 and 18 October,1993. Allinsertion 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 included in Table 18.
Thermal Hvdraulic Limits And Power Distribution:
The core maximum fraction of critical power (CMFCP), the core maximum fraction of limiting power density (CMFLPD), the maximum average planar linear heat generation rate ratio to its limit (MAPRAT) and the ratio of CMFLPD to the fraction of rated power (FRP) were all checked daily during the startup using the process computer. All checks of core thermal limits were within the limits specified in the Technical Specifications.
The process computer distribution was calibrated five times using the traversing incore probe (TIP) system during the ascent to full power. The results of these updates are presented in Table 11.
The LPRMs were manually calibrated once in conjunction with the TIP system.
The LPRM high and low trip alarm set points were verified correct prior to startup on October 18,1993. All LPRM operating voltages and the initial calibration currents for two new LPRM strings were set prior to startup. The TIPS and the LPRMs were both functionally tested and found to operate satisfactorily. A total of 10 APRM gain adjustments were done as required during the startup from October 25 through 28,1993.
The process computer power distribution update performed on November 2, 1993 (TIP set 1491) was used as a basis for comparison with an ,off lin.e calculation performed using the Yankee Atomic Electric Company nodal code SIMULATE-3. For that power distribution, the SIMULATE-3 core average axial power distribution was compared to that calculated by the plant process computer. Comparisons are shown in Table Ill. A comparison was also performed between SIMULATE-3 and process computer peak radial power. These comparisons are shown in Table IV.
At approximately 25, 50, 75 and 100 percent power levels the process computer heat balance was compared with an off-line computer calculation. The values of core thermal power from each method were found to be in excellent agreement (within 3 Megawatts thermal).
A core flow calibration was successfully completed on November 11,1993 to ensure that the core flow calculation by the process computer is accurate over entire operating range.
TIP Reoroducibility And TIP Svmmetrv:
TIP system reproducibilty was checked in conjunction with the power distribution update performed on October 26,1993. All three TIP system traces were reproducible to within 2.9%. A TIP intermachine calibration was successfully completed on October 26,1993. A check of tip axial alignment was completed on December 3,1993 and found to be acceptable.
The total TIP uncertainty was calculated using TIP set 1491. Since the rod pattern was nearly symmetric, the actual plant TIP readings were used in the calculation. The resulting total TIP uncertainty for this case was 1.35%. The results of the TIP uncertainty test as shown in Figure 111 are well below the 8.7% acceptance criteria.
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3-i TABLE IA i CONTROL ROD SCRAM TESTING RESULTS -
! VERMONT YANKEE BEGINNING OF CYCLE 17 ,.
4 1
] Single Rod Scrams _ Cold Hydro - 17 and 18 October, 1993 2
o Maximum 92.01% insertion time (seconds) = 2.731 Tech. Spec. Limit for slowest 90% insertion time (secor.ds) = 7.000 Mean time for % insertion 4.51% 25.34% 46.18% 87.84%
i j Measured time (sec) 0.313 0.820 1.337 2.426 1 Tech. Spec limit (sec) 0.358 0.912 1.468 .2.686 1
i i Slowest 2x2 array for % insertion 4.51% 25.34% 46.18% 87.84%
i l Measured time (sec) 0.327 0.838 1.361 2.470 l
Tech. Spec. limit (sec) 0.379 0.967 1.556 2.848 -
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!' TABLE IB
! CONTROL ROD SCRAM TIME RESULTS
- VERMONT YANKEE CYCLE 17 Single Rod Scrams at Power - October 15, 1992 j Maximum 92.01% insertion time (seconds) = 2.883 j Tech. Spec. Limit for slowest 90% insertion time (seconds) = 7.000 Mean time for % insertion 4.51% 25.34% 46.18% 87.84%
l i Measured time (sec) 0.354 0.865 1.385 2.480
- Tech. Spec. limit (sec) 0.358 0.912 1.468 2.686 Slowest 2x2 array for % insertion 4.51% 25.34% 46.18% 87.84%
l
! Measured time (sec) 0.391* 0.919 1.442 2.548 Tech. Spec. limit (sec) 0.379 0.967 1.556 2.848 i
- Reportable Occurrence No. LER 93-05, Supplement 1, dated 8/15/93.
s 4 Single Rod Scrams at Power - April 6, 1993 Maximum 92.01% insertion time (seconds) = 3.040 Tech. Spec. Limit for slowest 90% insertion time (seconds) = 7.000 Mean time for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.369* 0.871 1.380 2.454 Tech. Spec. limit (sec) 0.358 0.912 1.468 2.686 Slowest 2x2 array for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.405* 0.913 1.442 2.577 Tech. Spec. limit (sec) 0.379 0.967 1.556 2.848
- 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Enforcement Discretion received from NRC. However, a plant shutdown was initiated on April 6 due to an unrelated issue.
Reportable Occurrence No. LER 93-05, Supplement 1, dated 8/15/93.
__________________m_____________________________________________________________
Single Rod Scrams - Cold Hydro - April 15, 1993 Maximum 92.01% insertion time (seconds) = 2.853 Tech. Spec. Limit for slowest 90% insertion time (seconds) = 7.000 Mean time for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.324 0.839 1.360 2.462 Tech. Spec. limit (sec) 0.358 0.912 1.468 2.686 Slowest 2x2 array for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.340 0.886 1.432 2.558 Tech. Spec. limit (sec) 0.379 0.967 1.556 2.848
- - - - - - - ~
.-. -- - .- . . . _ - . - . _ - . - -.- _ - _ - - - ~ - - - . - -
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. TABLE IB (cont'd) j CONTROL ROD SCRAM TIME RESULTS 4 VERMONT YANKEE CYCLE 17
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3 Single Rod Scrams at Power - April 17, 1993 Maximum 92.01% insertion time (seconds) = 2.789 '
Tech. Spec. Limit for slowest 90% insertion time (seconds) = 7.000 4
Mean time for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.312 0.815 1.323 2.394
! Tech. Spec. limit (sec) 0.358 0.912 1.468 2.686 i
, Slowest 2x2 array for % insertion 4.51% 25.34% 46.18% 87.84% '
4 Measured time (sec) 0.322 0.859 1.409 2.553 Tech. Spec. limit (sec) 0.379 0.967 1.556 2.848 4
Single Rod Scrams at Power - June 6, 1993 Maximum 92.01% insertion time (seconds) = 2.720 Tech. Spec. Limit for slowest 90% insertion time (seconds) = 7.000 Mean time for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.316 0.818 1.325 2.390 Tech. Spec. limit (sec) 0.358 0.912 1.468 2.686 Slowest 2x2 array for % insertion 4.51% 25.34% 46.18% 87.84%
Measured time (sec) 0.323 0.859 1.409 2.553 Tech. Spec. limit (sec) 0.379 0.967 1.556 2.848 l
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- TABLE II Vermont Yankoo Power Distribution Measurements Cycle 17 Start-Up Core Date Time Power (%) Flow (%) CMFLPD CMFCP MAPRAT
____ ____ _______ _______ ______ _____ ______ q 0.607 0.643 10/26/93 16:27 57.0 49.0 0.539 10/26/93 21:42 54.7 49.2 0.546 0.620 0.489 10/27/93 06:03 78.3 59.9 0.784 0.797 0.671 10/28/93 10:17 99.7 94.3 0.913 0.825 0.888 10/28/93 21:31 97.6 89.2 0.932 0.826 0.857 The Tech. Spec. limit for the three thermal limits above is less than or equal to 1.0.
l TABLE III Comparison of Process Computer and SIMULATE-3 Core Average Axial Relative Power Distributions Vermont Yankee Beginning of Cycle 17 Process Node SIMULATE-3 Computer 25 0.097 0.110 24 0.176 0.184 23 0.436 0.458 22 0.561 0.602 21 0.649 0.704 20 0.759 0.800 19 0.862 0.909 18 0.950 0.998 17 1.066 1.100 16 1.183 1.215 15 1.241 1.268 14 1.255 1.261 13 1.309 1.305 12 1.337 1.331 11 1.346 1.320 10 1.341 1.301 9 1.358 1.330 8 1.362 1.326 7 1.354 1.270 6 1.366 1.302 5 1.367 1.306 4 1.317 1.237 3 1.178 1.108 2 0.889 0.833 1 0.241 0.418
TABLE IV Comparison of 10 Highest Relative Radial Powers Vermont Yankee Beginning of Cycle 17 1
Process Location Computer SIMULATE-3 27-16 1.277 1.268 29-18 1.270 1.264 27-14 1.260 1.293 33-20 1.247 1.251 29-16 1.242 1.239 27_12 1.240 1.248 25-18 1.239 1.225 33-18 1.236 1.240 27-20 1.236 1.219 31-18 1.235 1.282 i
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644 l# 644 l#S8S # $85 l# us 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 g LPRM LOCATION (COMMON LOCA710N 43 FOR ALL TIP MACHINES 8
Q LPRM LOCATION (LEYTER INDICATES flP MACHINE) 35 l l 31 l
@ IRM LOCATION 27 l 23 l
[ SRM LOCATION 19 l
l l 15 l l 11 1I I l 01 l l l l l c3 I Iij ;
! 02 os to 141s 22 26 30 34 as 42 i
'. o Figure 11 Vermont Yankee Beginning of Cycle 17 CRITICAL ROD CONFIGURATION COMPARISON 43 48 26 39 35 48 48 31 48 48 48 27 48 48 48 48 48 48 48 48 23 19 48 48 15 48 22 48 11 48 48 48 48 48 07 03
-1% AK/K @ 150*F Predicted Critical Pattern @ 150*F 02 06 10 14 18 22 26 30 34 38 42 02 06 10 14 18 22 26 30 34 38 42 12 43 48 48 48 48 48 48 48 48 39 12 ,
12 35 48 48 48 48 48 48 48 31 12 14 12 27 48 48 48 48 48 48 48 48 48 48 48 48 23 12 12 12 39 48 48 48 48 48 26 48 5
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gg 48 48 48 48 48 48 48 48
. 07 12 03
+1% AK/K @ 150*F Actual Critical Pattern @ 158'F No te : A blank box denotes rod position 00 l
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Figuro III
39 -------------
35 --------
31 -------- 34 22 34 27 ---
23 --- 20 18 20 19 ---
l 15 -------- 34 22 34 11 --------
1 I l 07 -------------
03 02 06 10 14 18 22 26 30 34 38 42 TIP: 1491 Date: November 2, 1993 CTP: 99.9%
Core Flow: 97.4%
Uncertainty: 1.35%