ML20117N048
| ML20117N048 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/10/1996 |
| From: | Mccollum W DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-96-001, IEB-96-1, TAC-M95019, NUDOCS 9609180316 | |
| Download: ML20117N048 (6) | |
Text
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1 L
.1)ukennwr Company WawstK McCu.uu.Je 1
Catauha Nuclear Generation thpartment.
Vice"nnident i
4H00 ConcordRotui (812)331J WIOffice L
York, SCT3745 (803)S3135Far s
9--
September 10,1996 l
l U.S. Nuclear Regulatory Commission l
ATTENTION: Document Control Desk Washington, DC 20555-0001 i
SUBJECT:
Duke Power Company 1
j Catawba Nuclear Station - Unit 2 i
Docket No. 50-414 NRC Bulletin 96-01 Test Data
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The purpose of this letter is to provide information on Catawba Unit 2 actions taken during the recent forced outage of August 2,1996 in response to NRC Bulletin 96-01.
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NRC Bulletin 96-01, dated March 8,1996, requested holders of operating licenses for i
Westinghouse designed plants to take actions and supply information to the NRC regarding L
recent control rod insertion problems. The initial Duke Power response to this bulletin was.
{
. provided by letter dated April 4,1996 and supplemented with additional information by I
letters dated April 30,1996 and June 7,1996. Catawba Unit I refueling outage test data were also submitted to your staff by letter dated August 29,1996.
Restated below are pertinent sections of the NRC Bulletin 96-01 requiring actions during any outages of sufficient length at Catawba during calendar year 1996:
Requested Action (3):
(3)
Measure and evaluate at each outage of. sufficient duration during calendar year l
1996 (end of cycle, maintenance, etc.), the control rod drop times and rod recoil l
data for all control rods. If appropriate plant conditions exist where the vessel head is removed, measure and evaluate drag forces for all rodded fuel assemblies.
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a.
Rods failing to meet the rod drop time in technical specifications l
shall be deemed inoperable.
b.
Rods failing to bottom or exhibiting high drag forces shall require prompt corrective action in accordance with Appendix B to Part 50 i
. of Title 10 of the Code of Federal Regulations (10 CFR Part 50).
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9609180316 960910
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PDR ADOCK 05000414 G
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U.S. Nuclear Regulatory Commission September 10,1996
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Page 2 l
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Required Response Item (3).
(3)
Within 30 days after completing Requested Action (3) for each outage, submit a report that documents and summarizes the data obtained. This is also applicable to Requested Action (4) when any abnormal rod behavior is observed.
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Catawba Response to Item (3):
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Included as an attachment to this letter is a summary report of the Catawba Unit 2 control rod drop data for Requested Action (3) obtained during the Unit 2 forced outage which began August 2,1996. This testing was completed on August 11,'1996.
I Catawba Nuclear Station has no further refueling outages planned for the remainder of 1996. However, if future outages of sufficient duration occur in 1996, data requested in
[
. 96-01 will be collected as described in Duke Power's response to your staff, dated April 4,-1996. Duke Power continues to have 100% successful rod insertions in Mark BW fuel and continues to have substantial margin to the required Technical Specification insenion i
times. Please direct any questions on this matter to Jeff Lowery at (803) 831-3414.
I declare, under penalty of perjury, that the statements set forth herein are true and correct
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to the best of my knowledge.
Very truly yours, Y
/
W. R. McCollum Jr.
t i
I Attachment l
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I r
l
i U.S. Nuclear Regulatory Commission September 10,1996 J
Page 3 -
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I xc:
S.D. Ebneter, Regional Administrator, Region II R.J. Freudenberger, Senior Resident Inspector P.S. Tam, Senior Project Manager, ONRR 1
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4 i
n i
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l Catawba Nuclear Station f
NRC Bulletin 96-01 Attachment Unit 2 Forced Outage Control Rod Drop Testing Results On August i1,1996 Control Rod Drop Timing was performed in accordance with the I
requirements of NRC Bulletin 96-01. The following is a summary of the data analysis of the oontrol rod drop testing results for Catawba Nuclear Station Unit 2.
During the recent Unit 2 forced outage (August 2,1996), Control Rod Drop Timing Testing was performed on the Control Rod Drive Lines and Rod Control Cluster Assemblies (RCCAs). This included a detailed analysis of control rod drop times and rod recoil data (see attached table).
Catawba Nuclear Station has trended control rod drop times since initial plant startup in 1986.
The data have been consistent during all testing on both Unit I and Unit 2.
i The test method used consisted of selecting a control rod bank, withdrawing the bark to the hard rod stop (231 steps), removing power from both Digital Rod Position Indication (DRPI) System 4
Data Cabinets (Data A and Data B), dropping each individual RCCA by removing its Movable 1
Gripper (MG) and Stationary Gripper (SG) fuses, recording the voltage profile induced by the j
RCCA drive shaft as it dropped through the coils of its associated DRPI detector, restoring power to both DRPI Data Cabinets, verifying each RCCA completely inserted, and repeating this test method until all 53 control rods had been tested. All testing was performed at full temperature and pressure with all four Reactor Coolant Pumps running.
The analysis method used consisted of a detailed review of each control rod's time based profile.
The individual drop time for each RCCA was determined by analyzing the recorded voltage profile and are shown in the attached table. Three rods, H08, M02, and M14, were observed as having slightly longer drop times. These rods were identified by calculating two standard deviations from the average drop time and comparing the recorded voltage profiles of each rod. The profiles of eight rods were superimposed on each other and compared. The mean profile was used to compare l
an additional seven rods. This process was repeated until all of the rods were analyzed. All rod drop tines were well within the Tech Spec required time of s 2.2 sec. The average control rod drop time was 1.554 sec. with an average rod bottom time of 2.082 sec. Catawba rod drop traces did not reveal any change at the top of the fuel assembly.
The rod drop traces were analyzed for rod recoil (an indication that the rod is fully inserted to rod bottom). All the recorded rod drop traces exhibited rod recoil with a minimum of 2 recoils for i
each RCCA.
Duke Power has detailed information on the testing and analysis methodology. This information is available to the NRC upon request.
Catawba Unit a Forced Outage Control Rod Drop Teseng Results I
I BOC-8 i
a I SHUTDOWN tapprommate8y 230 EFPD) i i
1 Shutocwn - BOC i
i 11/26/95 i Bumup i
i i 8/11/96 4 i Burnup i
i i
Core Loc ; Time to DP iTime in DP iTotal Time i MWD /MTU 6
- Time to DP i Time in DP Total Time 1 MWD /MTU i Recoets i
- ? Time to OP r Time M DP : Total Trne H06 1.560 0.527 2.087 19640 1.565 1
0.526
' 2.091 297_90 1 2
1 0.005
-0.001_,,_0.004_
H10 1.537 0.512 2.049 19891 1.542 0.508 2.050 29940 3
0.005
-0.004 0.001_
F08 1.561 0.488 2.049 19821 1.586 t 0.529 2.115 29910 3
0.025 0.041 0.066 7 08 1.6i6 0 595 2 211 19626 inewrod 1.564 i
0.593 2357 29_740 2
-0.052
-0.062
-0[05_4]
~
H02 1.600 0.630 2_.230 __22_064inew rod 1.539 0.595 2.134 30320 3
i
-0.061 1
-0.035
-0.096_
B08 1.556 0.490 2.046 21728 1.533 0.491 2.024 30090 3
i
-0.023 1
0.001 0.022 H14 1.580 0.496 2.076 21337 1.562 0.509 2.071 29620 3
-0.018 0.013
-0.005 PO8 1.547 0.492 2.039 21847 1.533 0.510 2.043 30020 4
-0.014 0.018 0.004
_ F06 1.562 0.531 2 093 24545 1.599 0.545 2.144 34140 3
0.037 0.014 f0.051_
F10 1.558 0.550 2.1_08 24650 1.561 0.576 2.137 i 34310 3
0.003 0.026 ! 0.029 _
K10 1.521 0.538 2.059 24543 1.527 0.558 2.085 i 33990 3
0.006 0.020 0.026 K06 1.542 0.533 2T075 2i463 1.577 0.557 2.134 i 34350 2
0.635 0.024 0.059-D02 1.623 0.579 2.202 21485 1.592 0.577 2.169
! 26780 3
-0.031
-0.002
-0.033 B12 1.591 0.507 2._098
__21102 1.592 0.509 2.101 l 26530 3
0.001 0.002
_ 0.003 M14 1.618 0.572 2.190 21562 1.614 0.561 2.175 1 26980 3
-0.004
-0.011
-0.015 PO4 1.607 0.499 2.106 21673 1.576 0.493 2.069 27150 3
-0.031
-0.006
-0.037 804 1.573 0.532 2.105 21720 1.533 0.510 2.043 27220 4
-0.040
-0.022
-0.062
_ D14 1.575 0.532 2.107 2_14_16 1.574 0.526 2.100 26820 3
-0.001
-0.006
-0.007_
P12 1.575 0.501 2.076 21473 1.545 0.507 2.052 26860 3
-0.030 0.006
-0.024 M02 i 1.635 0.518 2 153 2'1297 1.614 0.526 I 2340 26690 3
6
-0.021 OT608
-0T013~-
__E03 1.560 __ 0.528 2.088 15587 1.555 0.508 I
2.063 25150 __3 j
-0.005
-0.020
-0.025_
C11 1.552 0.5_?S 2.068 15402 1.535 0.511 2.046 25300 3
-0.017_J
-0.005
-0.022
__Q3 1.528 0.4_95 2.023 15726 1.517 0.507 2.024 25_580 3
-0.011 0.012 0.001 _
N05 1.543 0.528 2.071 15713 1.543 0.525 2.068 25490 3
0.000
-0.003
-0.003 C05 1.529 0.469 1.998 15800 1.536 0.507 2.043 25670 4
0.007 0.038 0.045 E13 1.583 0.552 2.135 15880 1.589 0.561 2.150 25730 2
0.006 0.009 0.015 N11 1.531 0.493 2.024 1528_8 1.511 0.511 2.022 24960 4
-0.020 0.018
_-0.__ 02_
0 LO3 1.590 0.605 2.195 15960
'new rod 1.555 0.611 2.166 26010 2
-0.035 0.006
-0.029
__ _04 1.546 0.559 2.10_5 20787 1.i67 0.542 2.109 31320 2
{
0.021
-0.017 0.004__
H DOB 1.555 0.545 2.100 21014 1.561 0.542 2.103 31680 3
i f
0.006
-0.003 0.003 H12 1.553 0.498 2.051 20467 1.571 0.494 2.065 31070 3
0.018
-0.004 0.014 M08 1.584 0.556 2.140 21200 1.564 0.526 2.090 31820 2
-0.020
-0.030
-0.050 F02 1.589 0.506 2.095 11085 1.562 0.526 2.088 20330 3
-0.027 0.020
-0.007_
B10 1.563 0.515 2.078 10984 1.532 0.525 2.057 20410 3
-0.031 0.010
-0.021 K14 1.564 0.515 2.079 10867 1.535 0.508 2.043 20180 4
-0.029
-0.007 l -0.036 P06 1.515 0.529 2.044 11038 1.507 0.509 2.016 20440 4
-0.008
-0.020 i -0.026
_B_06 1.572 0.550 2.1_22 10851 1.571 0.541 2.112 20360 3
l
-0.001
-0.009
-0.01_0__
F14 1.574 0.529 2.103 11266 1.558 0.524 2.082 20830 3
-0.016
-0.005
-0.021 P10 1.536 0.500 2.036 11020 1.515 0.493 2.008 20230 3
-0.021
-0.007
-0.028 K02 1.617 0.522 2.139 11186 1.593 0.527 2.120 20770 3
-0.024 0.005
-0.019 D04 1.548 0.481 2.029 20132 1.549 0.506 2.055 30060 4
0.001 0.025 0.026 M12 1.582 0.617 2.199 19971 newtod 1.524 0.563 2.087 29980 3
-0.058
-0.054
-0.112 D12 1.563 0.472 2.035 19882 1.543 0.492 2.035 29970 3
-0.020 0.020 0.000 M04 1.599 0.509 2.108 19885 1.583 0.511 2.094 29940 3
-0.016 0.002 i
-0.014 t
Page1
Catawba Unit 2 Forced Oit. age Control Rod Drop Tesung Results 6.
H06 1.602 0.521 2.123 32941 l 1.631-0.542 2.1TJ 41170 3
0.029
- 0.021 0.050 G03 1.530 0.622 2.152 17733 'new rod 1.518 0.594 2.112 27680 2
-0.012
-0.028
-0.040 '
C09 1.531 0.521 2.052 17633 1.543 0.509 2.052 27600 3
0.012
-0.012 0.000 J13 1.540 0.555 2_.095 17958 1.536 0.527 2.063 27930 3-
-0.004 -
4.028
-0.032 N07 1.530 0.507 2.037 17644 1.513 0.492 2.005 27630 4
-0.017
-0.015
-0.032_
C07 1.534 0.513 2.047
-17823 1.552 0.508 2.060 27920 3
0.018
-0.005 0.013 _
G13 1.542 0.500 2.042 17616 1.521 0.507 2.028 27640 3
-0.021 0.007
-0.014 N09 1.529 0.523 2.052 17565 1.511 0.523 2.034 27440 3
-0.018 0.000
-0.018 J03 1.575 0.506 2.081 17556 1.522 -
0.540 2.062 27560 3
-0.053 0.034
-0.019 Average 1.565 0.528 2.093 18629 1.554 0.529 2.082 27681 3
-0.011 0.001
-0.010 Page 2
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