M950159, Forwards Voluntary Results of Control Rod Drop & Drag Testing on Catawba Unit 2 at End of Cycle 8,in Response to NRC Bulletin 96-01

Forwards Voluntary Results of Control Rod Drop & Drag Testing on Catawba Unit 2 at End of Cycle 8,in Response to NRC Bulletin 96-01

ML20141K968
Person / Time
Site:	Catawba
Issue date:	05/21/1997
From:	Mccollum W DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-96-001, IEB-96-1, TAC-M950159, NUDOCS 9706020197
Download: ML20141K968 (8)

Text

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i. I Dukelhun Company WimwR. S1d'ow n, J&

Qataubo Nwlear Generation Departinent fiahcstdent 4800 ConcordR>ad (8M)Dia.M Offe-York, SC29745 .

(SMJul4426 Fax 1

! DUKEPOWER l

l May 21, 1997 i

U.S. Nuclear Regulatory Commission Attention: Document Control Desk

! Washington, DC 20555-0001- l

! I

Subject:

Duke Power Company l Catawba Nuclear Station - Unit 2 l Docket No. 50-414

! RCCA Testing Results I (TAC M95019) l Although NRC Bulletin 96-01 expired at the end of 1996, Duke Power Jacided to voluntarily perform control rod drop and drag t; sting on Catawba 2 at the end of cycle 8 (2EOC8). The reactor core was comprised entirely of FCF Mark BW fuel.

'This letter provides the results of this testing.

l l Drop times to the dashpot and from the dashpot to rod bottom were measured for all rods and are provided in Attachment 1.

All. control rods dropped well within the Technical Specification required time of 2.2 seconds to the dashpot.

The average drop time for all rods was 1.58 seconds. The maximum burnup fuel assembly under a RCCA was 49,229

-MWD /MTU.

Attachment 2 provides the results of the in-pool drag tests.

From these data it can be seen that the maximum dashpot drag force was 50 pounds during withdrawal and that the maximum above dashpot drag force was 35 pounds during withdrawal.

Again, all RCCAs fully inserted well within the required  ;

I Technical Specification time, so these are acceptable drag forces. The drag forces are also considerably less than i

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-those measured at many other Westinghouse plants. I h

9706020197 970521 PDR ADOCK 05000414 g G PDR L l l , , ,

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, U. S. Nuclear Regulatory Commission May 21, 1997 Pa'ge 2 If you have questions concerning these data, please contact Richard Clark at 704-382-5823 or Martha Purser at 803-831-4015.

Sincerely, W. R. McCollum, Jr.

xc: Mr. Luis A. Reyer.

Regional Administrator, Region II U. S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St. SW, Suite 23T85 Atlanta, Georgia 30303 Mr. P.S. Tam U. S. Nuclear Regulatory Commission Mail Stop O-14 H25 Washington, D. C. 20555 Mr. R. J. Freudenberger NRC Senior Resident Inspector Catawba Nuclear Station U. S. Nuclear Regulatory Commission i

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Catawba Nuclear Station Attachment 1 Unit 2 EOC-8 Control Rod Drop Testing Results On March 21, 1996 Control Rod Drop Timing was performed. .

The following is a summary of the data analysis of the control rod drop testing results for Catawba Nuclear Station Unit 2. ,

! During the recent Unit 2 refueling outage (2EOC8), 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 1 and Unit 2. )

1 The test method used consisted of selecting a control rod j bank, withdrawing the bank to the hard rod stop (231 steps) , l removing power from both Digital Rod Position Indication )

(DRPI) System Data Cabinets (Data A and Data B), dropping the ]

entire bank of rods by opening both Reactor Trip Breakers, recording the voltage profile induced by the RCCA drive shaft as it dropped through the coils of its associated DRPI detector, rcstoring 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 l each control rod's time based profile. The individual drop i time for each RCCA was determined by analyzing the recorded ,

voltage profile and are shown in the attached table. Two  !

rods, F06 and H08, were observed as having slightly longer i 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. All rod drop times were well within the' Tech Spec required time of < 2.2 sec. The average control rod drop time was 1.58 sec. with an average rod bottom time of 2.13 sec.

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 1 recoil for each RCCA.

Catawba Unit 2 Control Rod Drop Testing Results

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4 i BOC-8 i i i i i EOC-8 i i i i ,

i EOC-BOC 1 ,

I i 11/26/95 t i Bumup i I t 3/21/97 I a Bumuo i l i 1 e Core Loc ! Time to DP i Time in DP e Iotal Time i MWD /M TU i i Time to DP i Time in DP t Totat Time i MWD /MTU l Recoils i i Time to OP l Time in DP l Total Time [

H06 1.560 0 527 2.087 19640 1.59 0.56 2.15 39012 2 0 030 0.033 0 063 H10 1.537 0.512 2.049 19891 1.54 0.53 2.07 39024 3 0 003 0 018 0 021 [

F08 1.561 0.488 2.049 19821 1.60 0.55 2.15 39021 2 0 039 0 062 0.101  !

K08 1.616 0.595 2.211 19626 new rod 1.59 0 61 2.20 38852 2 -0.026 0 015 -0011 H02 1.600 0 630 2.230 22064 newrod 1.55 0.61 2.16 37971 3 -0 050 -0020 -0070 B08 1.556 0.490 2.046 21728 1.53 0.52 2.05 37771 3 -0026 0.030 0 004 H14 1.580 0 496 2 076 21337 1.57 0.52 2.09 37158 4 -0010 0 024 0.014 '

P08 1.547 0 492 2.039 21847 1.54 0 52 2.06 37458 4 -0.007 0 028 0 021 F06 1.562 0 531 2.093 24545 1.67 0.63 1 2.30 43130 1 0.108 0 099 0.207 ,

F10 1.558 0 550 2.108 24650 1.61 0.59 [ 2.20 43278 2 0.052 0.040 0 092  !

K10 1.521 0.53_8 2.059 24543 1.55 0.58 2.13 42841 2 0 029 0 042 0 071 K06 1.542 0.533 2.075 24463 1.64 0.60 2.24 43583 1 0 098 0.067 0.165 ,

D02 1.623 0.579 2.202 21485 1.61 0 61 2.22 31742 3 -0013 0.031 0.018 B12 1.591 0.507 2.098 21102 1.63 0.54 2.17 31486 3 0 039 0.033 0.072 M14 1.618 0.572 2.190 21562 ~

1.59 0.59 2.18 32008 3 -0.028 0.018 -0.010

_PO4 1.607 0.499 2.106 21673 1.59 0.51 2.10 32181 3 -0017 0 011 -0.006 l B04_ 1.573 0.532 2.105 21720 1.52 0.54 2.06 32340 4 -0053 0.008 -0 045 D14 1.575 0.532 2.107 21416 1.58 0.55 2.13 31818 3 0 005 0 018 0.023 P12 1.575 0.501 2.076 21473 1.55 0.51 2.06 31806 5 -0,025 0.009 -0 016 M02 1 635 0.518 2.153 21297 1.61 0.55 2.16 31657 3 -0.025 0 032 0 007 E03 1.560 0.523 2 088 15587 1.59 0.54 2.13 33634 2 0.030 0 012 0 042 C11 1.552 0 516 2.068 15402 1.58 0.55 2.13 34038 3 0 028 0 034 0.062 L13 1.528 0495 2 023 15726 1.53 0.52 2.05 34320 3 0 002 0 025 0.027 i N05 1.543 0.528 2 071 15713 1.58 0.55 2.13 34122 2 0.037 0 022 0 059 C05 1.529 0 469 1.998 15800 1 57 0.52 2.09 34464 2 0 041 0.051 0.092 E13 1.583 0552 2.135 15880 1.63 0.64 2.27 34433 1 0 047 0.088 0.135 N11 1.531 0.493 2.024 15288 1.55 0.54 2.09 33451 3 0 019 0 047 0.066 LO3 1.590 0.605 2.195 15 % 0 new rod 1.56 0 62 2.18 34849 1 -0030 0 015 -0015 H04 1.546 0.559 2.105 20787 1.60 0.57 2.17 40588 2 0 054 0 011 0 065 D08 1 555 0.545 2.100 21014 1.57 0.56 2.13 41054 2 0.0'15 0 015 0.030 H12 1.553 0.498 2 051 20467 1 62 0.55 2.17 40366 2 0.067 0 052 0.119 M08 1.584 0.556 2 140 21200 1.59 0.56 2.15 41076 2 0.006 O_004 0 010 F02 1.589 0.506 2.095 11085 1.59 0.53 2.12 28409 3 0 001 0 024 0.025 B10 1.563 0.515 2 078 10984 1.57 0.52 2.09 28563 4 0 007 0 005 0 012 K14 1.564 0.515 2.079 10867 1.56 0.53 2.09 28333 4 -0.004 0 015 0.011 P06 1.515 0.529 2.044 11038 1.52 0.54 2.06 28597 3 0 005 0.011 0 016 B06 1.572 0.550 2.122 10851 1.60 0.55 2.15 28669 3 0 028 0 000 0 028 F14 1.574 0.529 2.103 11266 1 61 0 53 2.14 29193 3 0 036 0 001 0 037 P10 1.536 0.500 2.036 11020 1.55 l 0 52 2.07 28228 4 0.014 0 020 0.034 K02 1.617 0.522 2.139 11186 1.62 0.56 2.18 29162 3 0.003 0.038 0.041 D04 1.548 0 481 2 029 20132 1.55 0.52 2.07 38885 3 0 002 0 039 0241 M12 1.582 0.617 2.199 19971 new rod 1.54 0.58 2.12 38831 3 -0042 -0037 -0079 012 1.563 0 472 2.035 19882 1.58 0.54 2.12 38881 2 0 017 0068 0 085 M04 1.599 0509 2.108 19885 1 60 0.53 2.13 38818 3 0 001 0 021 0 022 I I I I i  ! t I I I i i l I

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Cttawba Unit 2 Control Rod Drop .esting Resutts i i BOC-8 e i e i I EOC-8 I I i e i t EOC-BOC t i i 11/26/95 i i Bumup i i 3/21/97 I i Bumup i i e t i Core Loc i Time to OP i Time in DP i Total Tune i MWD /MTu i t Trne to DP i Trne in DP I Total Trne i MWD /MTU I Recoils  : Tune to DP i Trne in OP l Total Time H08 1.602 0.521 2.123 32941 1.66 0 59 l 2.25 49229 2 0.058 0 069 0.127 G03 1.530 0.622 2.152 17733 new rod 1.56 0.61 1 2.17 36637 2 0 030 -0.012 0.018 C09 1.531 0.521 2.052 17633 1.58 0.55 2.13 36566 3 0.049 0 029 0.078 J13 1.540 0.555 2.095 17958 1.56 0.55 2.11 36889 3 0.020 -0005 0.015 N07 1.530 0.507 2.037 17644 1.53 0.51 2.04 36566 3 0.000 0.003 0.003 C07 1.534 0.513 2.047 17823 1.59 0.54 2.13 37053 2 0.056 0.027 0.083 G13 1.542 0.500 2.042 17616 1.58 0.53 2.11 36656 2 0.038 0.030 0.068 N09 1.529 0.523 2.052 17565 1.54 0.54 2.08 36266 3 0 011 0.017 0.028 J03 1.575 0.506 2.081 17556 1.59 0.54 2.13 36575 2 0.015 0.034 0.049 Average 1.565 0.528 2.093 18629 1.58 0.55 2.13 35803 3 0 015 0 026 0.0 11 i

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, Catawba Nuclear Station l Attachment 2 Unit 2 EOC-8 RCCA Drag Testing Results on April 3, 1997 Rod Control Cluster Assembly (RCCA) Drag l Testing was performed. The following is a summary of the data analysis of the End-of-Cycle (EOC) RCCA Drag Testing l results for Catawba Nuclear Station Unit 2. '

l l During the recent Unit 2 refueling outage (2EOC8), drag testing was performed on the Rod Control Cluster Assemblies l (RCCAs) in the Spent Fuel Pool after core unload. This included a detailed analysis of RCCA Drag Data (see attached  !

table for drag data). .

The control rod drag test arrangement consisted of a pancake load cell attached to the Spent Fuel Pool manipulator crane auxiliary hoist. The load cell was attached to the lifting.

bail of the Westinghouse Spent Fuel Pool RCCA grappling tool. The pancake load cell's analog output was connected to a digital indicator and strip chart recorder. The I Westinghouse RCCA grappling tool was then attached to each l RCCA. The total measured weight of the RCCA and tool was >

recorded using the strip chart recorder while withdrawing l and inserting each RCCA. Each RCCA was withdrawn 9 ft. and ]

then inserted to rod bottom. 1 The analysis method used consisted of a detailed review of each RCCA's weight profile. The maximum drag for each RCCA while in the dashpot and guide tube thimble for withdrawal and insertion was determined by analyzing the recorded voltage profile and is shown in Table 2. The weight of the i Westinghouse Spent Fuel Pool RCCA grappling tool was 40 lbs.

as measured submersed in the pool with no RCCA attached. The average measured weight of an RCCA and the tool was 112 lbs.

with the RCCA raised 9 ft and at rest. This weight was used as the reference weight. The recorded maximum drag for each i l

RCCA was calculated by determining the total weight at specific points on the drag traces and subtracting the reference weight (RCCA plus tool). All RCCA's were within the Westinghouse F-Spec tolerances. Catawba RCCA drag traces did not reveal any abnormalities of the fuel assemblies tested.

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