ML20140C748
| ML20140C748 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 05/29/1997 |
| From: | Barron H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-96-001, IEB-96-1, NUDOCS 9706100058 | |
| Download: ML20140C748 (5) | |
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McGuire hadear(Vnaatwn Department Iice newlent lDR)thigers Ferry Mxsd(MGonP)
(MI)37M890 lisniersulle, EC28078MIO (TN)SiHSDfar l-ouxepoWER l
-May 29, 1997 J.
l l-l U.S. Nuclear Regulatory Commission
-Attention:--Document Control Desk washington, DC 20555 l
l
Subject:
McGuire Nuclear Station, Unit 1 Docket No. 50-369
[
RCCA Testing Results NRC Bulletin 96-01, dated March 8, 1996, requested holders i
-of operating licenses for Westinghouse-designed plants to take actions and supply information to the NRC regarding recent control rod insertion. problems. The requirements of
[
Bulletin 96.01 expired at the end of 1996; however, McGuire voluntarily performed control rod drop testing on February-l 14, 1997 and rod drag testing on March 6, 1997 for Unit 1 l
end of cycle 11. The reactor core was comprised entirely of l
Framatone Mark BW fuel.
Drop times to the dashpot and from the dashpot to rod bottom were measured for all rods except those in Control Bank B.
j An unrelated electrical problem developed such that Coritrol Bank B could not be removed from the core for the drop test l
without a significant impact on the outage duration. Rod drop time data is provided in Attachment 1 for the remaining RCCAs.
"All rods were well within the Technical Specification i
required time of 2.2 seconds to the dashpot. The average drop time for all' rods was 1.38 seconds. The maximum burnup feal assembly under a RCCA was 51,850 MWD /MTU.
i
' Attachment 2 provides the results of the in-pool drag tests.
From this data. Th'e maximum dashpot drag force during withdrawal was 72 pounds and the maximum above dashpot' drag force during withdrawal was 63 pounds. These drag forces are r
within acceptable limits.
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U.S. Nuclear Regulatory Commission May 29, 1997 Page 2 Questions concerning this data, should be directed to Richard Clark at (704)382-5823 or Kay Crane at (704) 875-i 4306.
Sincerely, i
H.
B.
- Barron, ice President McGuire Nuclear Station
AttichmInt 1 McGuira 1 Cycb 11 RCCA Drop Time Difference Difference EOC EOC EOC EOC EOC-BOC EOC-BOC 2/14/97 2/14/97 2/14/97 Bumup ROD DASH POT ROD BOTTOM Time in Dashpot MWD /MTU Time to DP Time in DP B-4 1.304 1.604 0.300 28770
-0.046
-0.120 B-6 N/A N/A N/A 31340 N/A N/A B-8 1.376 1.796 0.420 28540 0.016 0.020 B-10 N/A N/A N/A 31200 N/A N/A B-12 1.343 1.683 0.340 28860
-0.017
-0.130 C-5 1.310 1.630 0.320 35020
-0.030
-0.100 C-7 1.327 1.627 0.300 39800
-0.013
-0.090 C-9 1.326 1.646 0.320 39910
-0.034
-0.100 I
C-11 1.329 1.689 0.360 35150
-0.021
-0.090 D-2 1.443 1.803 0.360 28540
-0.017
-0.160 D-4 1.379 1.820 0.441 35280 0.039 0.051 D-8 1.331 1,671 0.340 39360
-0.019
-0.080 D-12 1.439 1.900 0.461 35210 0.069 0.071 D 14 1.456 1.825 0.369 28840
-0.014
-0.111 E-3 1.308 1.668 0.360 35320
-0.042
-0.050 E-13 1.370 1.730 0.360 35000 0.000
-0.090 F-2 N/A N/A N/A 31070 N/A N/A F-6 1.397 1.877 0.480 38650 0.047 0.060 F-8 1.433 1.994 0.561 47630 0.073 0.121 F-10 1.398 1.978 0.580 39140 0.058 0.160 F 14 N/A N/A N/A 31400 N/A N/A G-3 1.306 1.626 0.320 39750
-0.054
-0.070 G-13 1.327 1.667 0.340 39690
-0.043
-0.050 H-2 1.436 1.916 0.480 28440 0.036 0.060 H-4 1.311 1.651 0.340 40030
-0.039
-0.080 H-6 1.372 1.352 0.480 47390 0.032 0.050 H-8 1.480 1.981 0.501 51850 0.100 0.101 H-10 1.412 1.933 0.521 47540 0.092 0.081 H-12 1.331 1.671 0.340 39560
-0.009
-0.080 H-14 1.477 1.917 0.440 28270 0.067 0.030 J-3 1.308 1.648 0.340 39590
-0.052
-0.080 J-13 1.326 1.666 0.340 39690
-0.054
-0.060 K-2 N/A N/A N/A 31620 N/A N/A K-6 1.398 1.898 0.500 38550 0.058 0.090 K-8 1.473 2.054 0.581 47310 0.103 0.111 K-10 1.438 1.958 0.520 38880 0.088 0.100 K-14 N/A N/A N/A 31190 N/A N/A L-3 1.330 1.670 0.340 35420
-0.020
-0.100 L-13 1.349 1.669 0.320 35150
-0.031
-0.070 M-2 1.485 1.825 0.340 28690
-0.005
-0.110 M-4 1.380 1.841 0.461 35160 0.050 0.061 M-8 1.332 1.672 0.340 39320
-0.028
-0.090 M 12 1.399 1.900 0.501 35190 0.059 0.061 M-14 1.584 1.984 0.400 28610 0.094
-0.010 N-5 1.309 1.609 0.300 35010
-0.041
-0.100 N-7 1.327 1.667 0.340 39600
-0.013
-0.090 N-9 1.348 1.708 0.360 39970
-0.002
-0.080 N-11 1.310 1.650 0.340 35240
-0.050
-0.020 P-4 1.344 1.644 0.300 28310
-0.006
-0.180 P-6 N/A N/A N/A 31230 N/A N/A t
P-8 1.397 1.797 0.400 28390 0.037 0.000 l
P-10 N/A N/A N/A 31350 N/A N/A P-12 1.325 1.625 0.300 28650
-0.035
-0.140 AVERAGE 1.375 1.770 0.395 35635 0.004
-0.029
. - Maximum Withdrawal and Insertion Drag Loads During Spent Fuel Pool RCCA Drag Test Drag Test Tool Reference Weight: 170 pounds RCCA UIEOCl1 Spent Fuel Withdrawal
. Insertion -
Reactor.
Withdrawal.
Elevation of.
Insertion Elevation of ID Fuel.
Pool
- Maximum Maximum VesselCore Maximum Maximum Maximum
- Maximum
- Assembly Storage
. Dashpot Dashpot Location F Outef-
~ Drag Load Out-of-Drag Load ID Location Drag Load Drag Load Reference.
Dashpot Drag Above the -
Dashpot Drag Above the
~ (Pounds)
(Pounds)
- Load '
Dash Pot '
Load Dash Pot (Pounds)
(Feet)
-(Pounds)
(Feet)
R39 AB16 H-7 25 48 C-11 18 1
9 1
R51 AB30 G-7 21 11 M-4 20 na^
10 na R55 AB24 F-7 29 22 E-3 17 1
10 1
R47 AA02 E-7 22 13 H-4 14 1
5 1
R04 AA01 D-7 19 12 C-7 12 1
3 1
R24 AA29 L-8 31 19 F-10 22 1
13 1
R41 AB64 K-8 20 12 L3 9
1 10 1
R44 AA43 J-8 16 6
N-7 9
1 1
1 R59 AB21 G-8 19 13 B-6 9
1 0
1 R48 AB46 F-8 25 17 C-5 10 1
2 1
R502 AB36 D-8 19 16 P-10 8
na 2
na R05 AB07 L-9 32 20 D-4 11 1
2 1
R57 AB32 J-9 18 9
K-2 7
na 2
1 R34 AA58 K-11 39 28 K-10 32 3
21 3
R40 AB22 F 11 36 28 D-12 23 1
17 1
R23 AA40 D-11 27 19 G-3 13 1
6 1
R20 AB67 D-12 14 3
M-12 9
na 1
na R50 AB13 F-12 37 29 E-13 21 3
14 2
R49 AAl2 K-12 39 30 H-12 19 1
10 1
R16 AA09 K-13 23 15 N-9 18 1
9 2
Note A: For all"na", the drag loads were consistent throughout the out-of-dashpot drag test distance of approximately 71/2 feet.
. (cont.)- Maximum Withdrawal and Insertion Drag Loads During Spent Fuel Pool RCCA Drag Test Drag Test Tool Reference Weight: 170 pounds RCCA U1EOCl1 Spent Fuel
-Withdrawal -
- Insertion -
Reactor.
= Withdrawal Elevation of Insertion :
. Elevation of ID l Fuel -
Pool _
Maximum Maximum Vessel Core Maximum.
LMaximum l Maximum ~
_DragImad Maximum TAssmibly -
. Storage Dashpot
.. Dashpot '
Location Out-of- -
Drag Load Out-of- -
ID Location -
' Drag Load
' Drag Load Referencef Dashpot Drag ~
Dash Pot
_: (Pounds)
(Feet)
Above the Dashpot Drag 1 Above the;
- (Pounds)
(Pounds)
Load Load Dash Pot (Pounds)
(Feet)
R156 AB63 H-13 17 7
L-13 9
na 2
na R36 K65 G13 54 42 H-10 50a 1
40
- 1 R19 K60 F-13 54 45 F-8 52" 1.5 38 1.5 R35 K35 E-13 35 24 H-8 29 8
19 8&3 R26 AB14 D-13 17 7
N-5 8
na 1
na R56 AA48 D-14 45 35 F-6 19 1
30 1
R22 K56 E-14 39 29 H-6 30 1
22 1
R17 Kl9 F-14 72 60 K-8 63 "
1 53 1
C 8
R500 AA47 H-14 15 16 C-9 10 na 0
na ROI AA05 K-14 19 12 J-13 12 na 1
na R15 AA46 K-15 37 29 G-13 31 1
21 1
R52 AA60 H-15 21 13 J-3 11 na 2
na R28 AA04 F-15 22 10 M-8 14 na 2
na RIO AB60 D-15 21 14 N-I l 16 1
9 1
R27 AA39 K-16 16 8
D-8 11 1
1 1
R21 AA08 H-16 18 10 K-6 14 1
7 1
R31 AB42 G-17 18 8
P-12 10 1
1 1
R08 AB50 E-17 18 8
K-14 7
na 3
na R42 AB51 E-18 13 5
P-4 8
na 1
na Note B: Drag load violates Westinghouse F-spec.
Note C: Highest dash pot drag load and within tolerance.
e (cont.) - Maximum Withdrawal and Insertion Drag Loads During Spent Fuel Pool RCCA Drag Test Drag Test Tool Reference Weight: 170 pounds tRCCAr iUIEOCl1f. Spent Fuel (Withdrawalf (Insertion ;
. iResetw1
?Withdrawali Elevahon of-Insertion
. Elevation of
- ?10
- Fuel '
Pool '
9MaxinnunT
' Maximum
- Vessel Core Maximum Maximum Maxinem -
Maximmen c
?Assemblyj jStorage Dashpot
- Dashpot Imationi; 5Out-of.
j DragI
[Out-of-t;.
IDrag; Load me E IDi Location 4
. Drag Load F rDrag Load?
E Reference Dashpot Drag 1Above tne ?
Desispat Drag!
.?Above thel a;
?(Poundsf;
%(Pounds)J syLoad!
TDash P0t k
[ Load [ '
Dash l Pot $
T
' ' ~
(Poundsb
' (Feet):
V(Pounds)I
- (Fset)i ~-
R38 AB59 H-18 19 12 B-10 13 na 3
7 R03 AB33 J-18 20 17 F-14 10 na 0
na R18 AB55 L-18 23 14 M-2 12 na 2
na R46 AB56 K-19 17 7
B-8 7
na 2
na R53 AB27 G-19 20 10 D-14 14 na 5
na R07 AB34 D-19 6
2 P-6 7
na 2
na R501 AB08 F-20 11 2
P-8 7
na 2
na R43 AB06 J-20 19 11 H-14 10 na O
na R32 AB54 L-21 29 19 B-12 18 1
8 1
R02 AB05 H-21 27 10 H-2 9
na 1
na Rll AB09 E-21 18 9
M-14 8
na 1
na R54 AB39 D-22 26 16 B-4 18 na 8
na R25 AB15 G-22 22 13 D-2 14 na 3
na R06 AB40 K-22 18 10 F-2 10 na I
na
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