ML20066H889
| ML20066H889 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/23/1991 |
| From: | Tremblay L VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BVY-91-10, NUDOCS 9101290315 | |
| Download: ML20066H889 (13) | |
Text
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.. s-IVERMONT YANKEE NUCl, EAR POWER CORPORATION-Ferry Road, Brattfeboro. VT 05301 7002 7
g ENGINEERING OFFICE i-580 MAIN $TREET OOL TON, M A 01740 (508)779 6711 l
January 23,1991 BVY 91 10 United States Nuclear Regulatory Commission NITN: -Document Control Desk Washington, DC 20555 i
References:
a.
License No. DPR-28 (Docket No. 50 271)
Subject:
Vermo-t ",nkee Cycle l' tartmp Test Rwart
Dear Sir:
(
- Enclosed please find the Cycle 15 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 Vennont Yankee i
' Technical Specifications.
'We trust that you will find.this information satisfactory; however, should you desire i
' additional information, please contact this office.
Very truly yours, l
VERMONT YANKEE NUCLEAR POWER CORPORATION (h $ N AM
'(,
1.conard A. Tremblay, Jr.
Senior Licensing Engineer Enclosure cc:
USNRC Region i Administrator USNRC Resident inspector VYNPS USNRC Project Manager-VYNPS 3 101290315 910123 b
DR. ADOCK 0500 1
D 0 04' E I
STARTUP TEST REPORT VERMONT YANKEE CYCLE 15 Introduction Vermont Yankee Cycle 15 initial startup commenced on 14 October 1990 following a 45.5 day outage for refueling and maintenance.
The core loading for Cycle 15 consists of:
104 BP8DRB299 Reinserts loaded in Cycle 13 48 DB324B Reinserts loaded in Cyclc 14 88 DD326D Reinserts loaded in Cycle 14 60 HP80WD311-100Z Non-irradiated assemblies loaded in-Cycle 15 64 DP8DFB311-11GZ Non-irradiated assemblies loaded in Cycle 15 4 ANFIX-3.04B-E0Z Non-irradiated qualification assemblies loaded in Cycle 15 An as-loaded Cycle 15 core map is included in Figure I.
Details of the Cycle 15 core loading are-contained in the Yankee Atomic Electric Company document YAEC-1749,
/ermont Yankee cycle 15 Core Performance Analysis Repcic", August 1990.
The final as-loaded core loading wasworified correct by Vermont Yankee and Yankee Atomic Electric Co. personnel on 26-27 Septe.nber 1990.
Control - rod coupling verification Las satisf actorily performed for all 89 control rods after control rod friction testing on 27 September 1990.- Control rod scram testing on all 89 rods was performed satisf accorily prior to reaching 30% core thermal power per the Technical Specifications.
The testing was performed on 9 October 1990.
An in-sequence critical was performed satisf actorily on 10 Octob'er 1990..The cold' shutdown margin was verified to be within the Technical Specifications based on data collected during the in-scquence critical.
Startup commenced on 14 October 1990 and full. power steady state conditions were reached on 24 October 1990.
Core Verification The final as-loaded core was verified correct on 26 and 27 September 1990. Three separate critaria were checked:
1.
Proper fuel bundle seating was verified by traversing'the core with the refueling orapple raised about 1/2" to 3/4" above three randomly selected peripheral bundles.
2.
Proper bundle orientation, channel f astener integrity and upper tie plate cleaniness woro verified.
Cne bundle was found' with a bent channel fastener.
The bundle was removed and the factoner was replaced and seating was reverified.
3.
Proper coro loading was verified by checking the serial number of each. bundle through the use of an underwater video camera. Two identical new fuel bundles were found to be switched.
The misloading was corrected. 'The verification was recorded on tape and later independently reviewed and reverified to agree with the licensed core loading shown in Figure I.
o 4
2
.-Process Computer Data Checks Process computer data shuffling checks were completed on 12 October 1990.
These checks i
j included various ma.aal and computer checks of the new data constants.
A check for consistency of the data was also performed by Yankee Atomic Electric Co. (YAEC) and found
[
to be satisfactory.
4 3
In-Sequence Critical Control rod sequence 15-A-2(1) was used to perform the in-sequence critical test.
On 10 October 1990 control rods were withdrawn in a normal startur sequence until criticality was achieved. Criticality was achieved on the last rod in Group 7 (22 49) at notch position 12.
The moderator temperaturn was 116 deg. F.
The actual critical rod pattern and the YAEC prediction agreed within +/- 1% delta-k/k.
Figure II-shows the actual, predicted and the +/- 1% delta-k/k critical rod patterns.
Cold Shutdown Margin Testing-The cold shutdown margin calculation was performed using the data collected during the in-
{
sequence critical.and information provided in the YAEC " Core Management. Report".
The i
minimum cold shutdown margin required was 0.32% delta-k/k. The actual was shown to be 2.34%
delta-k/k.
Control "od Scram Testing Single rod scram testing of all 89 control rods was performed sucessfully on 9 October 1990. All insertion times were within the limita defined in the Technical Specifications.
Results are presented in Table I-A.
-In accordance-with Technical Specifications Section 4.3.C.2, scram time information for scrams occurring since the transmittal of the previous startup test report are also included.
See Table I-B.
All scram time information s as evaluated to insure proper drive performance is being maintained.
No degradation of drive performance is noticeable.
Thermal Hydraulic Limits and Power Distribution The core maximum fraction of critical power (CMFCP), the core maximum fraction of limiting power density (CHFLPD), the maximum average planar linear heat generation ra ce ratio to its limit (MAPRAT) and the ratio of. CMFLPD to the fration of rated power (FRP) were all checked-3 daily during the startup using the process computer. All checks of core thermal limits were within the limits specified in the Technical Specifications.
j The process computer power distribution was updated four times using the Traversing Incore P
Probe (TIP) system during the ascent to full power. The results of these updates and the k
rated power case are presented in Tablo II.
The Local Power Range Monitors (LPRMs) were calibrated twice in conjunction with TIP sets.
The LPRM high and low trip alarm setpoints were verified correct prior to startup on l
12 October 1990.
The T7Ps and LPRMs were both functionally tested and found to operate satisfactorily.
{
l I
3
'The process computer power distribution update performed on 24 October 1990 (TIP set 1362) was used as a basis for comparison with an of f line calculation perf ormed using the Yankee Atomic Electric Co. nodal computer code SIMULATE-3.
For that poerr distribution the SIMULATE-3 core average axial power distribution was compared to ' that calculated by the plant process computer; comparisons are shown in Table III. A comparisca was also performed between SIMULATE-3 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 24 October 1990. All three TIP system traces were reproducible to within 1.5%.
The total TIP uncertainty was calculated using TIP set 1362. Since the control red patterr.
was nearly symmetric, the actual plant TIP readings were. ied in the calculation.
The resulting total TIP uncertainty for this case was 1.5%.
The results of the TIP uncertainty test as shown in Figure.III are well below the 8.7% acceptance criterion.
j l
i
4 Table I-A Control Rod Scram Testing Resulte Vermont Yankee Beginning of Cycle 15 Single Rod Scrams - 9 October 1990 Maximum 87.84% insertion time (secc. ids) = 2.923 Tech. Spec, limi* for slowest 87.84% insertion time (seconds) = 7.000 m
25.34%
46.18%
87.84%
dtqILL' me f or % incertion Measured time (seconds) 0.349 0.867 1.398 2.522 Tech. Spec. limit (seconds) 0.358 0.912 1.468 2.686 Slowest 2x2 arrav for % inpertion Measured time (seconds) 0.372 0.899 1.430 2.564 Tech. Spec. limit (seconds) 0.379 0.967 1.556 2.848
4 4
4 5
Table I-B Control Rod Scram Testing Results l
Vermont Yankee Cycle 14 i^
h Single Rod Scrams at Power - 23 September 1989 Haximum 87.84% insertion time (seconds) = 2.976 1 Tech. Spac. limit for slowest 87.84% insertion time (seconds) = 7.000 1
4.51%
25.34%
46.18%
87.84%
Mean Time.for % insertion Heasured time (seconds) 0.344 0.855 1.373 2.478 Tech. Spec. limit (seconds) 0.358 0.912 1.468 2.686 F
Slowest 2x2 arrav for % insertion 4
Measured time (seconds) 0.371 0.896 1.437 2.587 Tech. Spec. limit (seconds) 0.379 0.967 1.556 2.848 i
e.
L I
Single Rod Scrams - 19 March 1990 I
Maximum 8'.
4% incertion time (seconde) = 2.976 Tech. Spec. ILmit for elowest 87.84% insertion time (seconds) = 7.000 l
4,51%
25.34%
46.18%
87.84%
j; Mean Time.for % insertion Measured time iceconde) 0.355 0.876 1.402 2.521 Tech. Spec. limit (soccads) 0.358 0.912 1.468 2.G86 L
elowoot 2x2 arra.v for % insertion l
I Measured time (secondo) 0.377 0.929 1.476 2.634 l
Tech. Spec. limit (secondo) 0.379 0.967 1.556 2.848 J>
l S
l e
is I.
l l
l i
l it -
=
a l
6-
. Table I-B (cont'd)
Control Rod Scram Testing Results Vermont Yankee Cycle 14 Full Scram - 21 March 1990 Maximum 87.84% insertion time (seconds) = 2.976 Tech. Spec. limit for slowest 87.84% insertion time (seconds) = 7.000 4.51%
25.34%
46.18%
87.84%
B23n' Time for %. insertion Maasured timo (seconds) 0.324 0.834 1.350 2.454 Tecit. Spec ~. limit (seconds) 0.358 0.912 1.468 2.686 glowest 2xP arrav for % insertion Moasured time (seconds) 0.341 0.860 1.402 2.553 Toch. Spoc. - limit (seconds) 0.379 0.967 1.556 2.848 Full Scram - 1 June 1990 Maximum 87.84% insertion time (seconds) = 3.012 Toch. Spec. limit for slowest 87.04% insortion time (seconds) = 7.000 l
L 4 111 25.34%
46.18%
87.84%
2 f
Mean Timo for % insertion l
b Moasured time (seconds) 0.254 0.743' 1.241 2.318
~ Tech. Spec. limit (soconds) 0.358 0.912 1.468 2.686 Slowest 2x2 arrav for % insortion Monsured time (seconds).
0.276 0.807 1.344 2.494 Toch. Spec. limit (seconds) 0.379 0.967 1.556 2.848 l
i-
~.. -
- - ~ - -
e.
7 Table II Power' Distribution Metsurements Vermont Yankee Beginning of Cycle 15 2nist Time
%.CTP
% Flow CHFLPD CMFCP MAPRAT 18 Oct. 90 1831 44.4 49.2 0.536 0.607 0.515 19 Oct. 90 0652 59.3 49.4 0.672 0.733 0.649 19 Oct. 90 2102 74.6 62.2 0.753 0.793 0.726 21 Oct. 90 0814 74.4 60.4 0.742 0.797 0.721 24 Oct. 90 1045 99.6 99.5 0.916 0.865 0.891 The Tech. Spec. limit for the three thermal limite above is '
.as than or equal to 1.0.
i l
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l 1
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' O 8
a Table III Comparison of Process Computer and SIMULATE-3'-
Core Average Axial Power Distributions j.
-Vermont Yankee Beginning of Cycle 15 Process flode Comeuter SIMULATE-3 25 0.140 0.140 24 0.320'-
0.325 23 0.543 0.551 22-0.687 0.682 21 0.784 0.771
~!
20 0.869 0.877 19 0.963 0.966 18 1.019 1.023 17 1.086 1.099 16 1.174 1.176 15 1.206 1.199 11 1.202 126 l
12 1.227 1.216 l
.11 1.218
-1.214 10
'1.195
'1.211 9
1.241 1.242 8
1.271 1.283 7
l'.275 1.335 6
1.330 1.383 5
1.337 1.387 4
1.285 1.331 3
1.141 1.2.60 2
0.858 0.826 l
1 0.452 0.221.
4 e
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l
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9 Table IV Comparison of Ten Highest Relative Radial Powers Varrr.ont Yankee Beginning of Cycle 15 Process Location Computer SIMULATE-3 29-12 1.263 1.266 25-16 1.230 1.246 33-20 1.245 1.245 33-18 1.262 1.243 35-18 1.237 1.243 27-12 1.259 1.241 27-10 1.233 1.241 25-12 1.235 1.239 33-16 1.262 1.267 29-18 1.231 1.222
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k
Figure I CYCLE 15 C00.E MAP r
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1 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 t
g LPM LOCATION (COMMON LOCATION I
F01t ALL TIP MACHINIS) 43 Q (fitM LOCATIO:t (LETTER UfDICATES 39 TIP MACHINZ) 3$
l G IPx LOCATION 31 A su LOCATION 23 19 I
l 13
(
11 1
1 l
3 r
2 6 to 14 18 22 26 30 34 38 42 l
I i
l
'p' 11 1
' Figure II Vermont Yankee Beginning of Cycle 15_
j Critical Rod Configuration Comparison t
08-l 43 4f 48 49-47-43 48 48' 48
[
39 I
I l
I 10 10 33 N
!b hk kN 4$-
kb 31 0%
10 08 l
27' 48 --
hb h3.
k9 48 kb kS' 4h kb N-23 (0
08..
10:
, 1, k
4h hk 15 08 08 u
hh 48 hk N
N kk 48 k$-
i 07 lb 03 i
-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 38 42 l2 43 kh hh kI 4E.
N N.
ht 43 39
($:
l8-I2' l2 35 47 49 48 h8-48 41 47 48 31 12.
42 12' 12.
12.
12-2r-42 49 48 4%
48-42 48 43 42 4%
42~
47 23 42 12.
48 12.
12:
12.
1, 40 47 48-48 48 48 47 48 1s-12 12 12.
Il y
u h[
4k kh-hk N
kk N
N 07 N
h 03
+1% aK/K_
Actual Critical Pattern Note: A blank box denotes rod position 00.
~_
~
Figure III 12 VERMONT YANKEE Total TIF Uncertainty 1'
i l
l 43 _______________________
39 -------------
l 35 --------
1 38 20 38 I -
31 --------
27 ---
20 12 20 23 ---
l l
19 ---
l 38 20 38 46 l
15 ---- ---
11 --------
l 07 -------------
1 I
03 _________________t 02 06 10 14 18 22 26 30 34 38 42 l
l TIP:
1362 DATE:
24 October 1990 CTP: 99.6%
i l
Core Flow:
99.5%
l Uncertainty:
1.5%
i
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