2CAN089006, Forwards Steam Generator Tubing Inservice Insp Rept 2R7 Refueling Outage.No Tubes Plugged.Apologizes for Delay in Submitting Info

Forwards Steam Generator Tubing Inservice Insp Rept 2R7 Refueling Outage.No Tubes Plugged.Apologizes for Delay in Submitting Info

ML20058L851
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/02/1990
From:	James Fisicaro ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN089006, 2CAN89006, NUDOCS 9008080227
Download: ML20058L851 (7)

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August 2, 1990 2CAN089006 i U. S. Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 Washington, DC 20555 J

Subject:

Arkansas Nuclear One - Unit 2 1 Docket No. 50-368 i License No. NPF-6 i Steam Generator Inspection Report for 2R7 '

l Gentlemen:

An inservice inspection was performed on selected tubes in steam generators 2E-24A and 2E-248 at Arkansas Nuclear One, Unit 2 during the period October 1-5, 1989. The number of tubes inspected was 386 in 2E-24A and 396 -

in 2E-24B; no tubes were plugged. In accordance.with ANO-2 Technical Specifications 4.4.5.5 and 6.9.1.5b, a report of the complete results'of the steam generator tube inservice inspections is attached. We apologize for the delay in submitting this information. The individual responsible for this report did not have a clear orderstand;ng of the required due date nor were procedures explicit with -+spect to the due date. This requirement was being tracked on management' =cacking program; however, it was not-recognized to have a specificat.j required technical specification due date.

A Condition Report has been initiated to address appropriate corrective action. Our failure to meet this due date was discussed with the ANO-2 NP.R ProjectManager.

If you have any questions regarding this report, please do not hesitate to contact my office, Very truly yours, gwl.YS" James J. Fisicaro Manager, Licensing JJF: DEJ: fc Enclosures UTOSOS6227 900802 PDR Q ADOCK 05000368 0 PDC i

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i U. S. NRC l Page 2 August 2, 1990 cc: Mr. Robert Martin l U. S. Nuclear Regulatory Comission l Region IV  !

611 Ryan Plaza Drive Suite 1000 Arlington, TX 76011. ]

NRC Senior Resident Inspector Arkansas Nucl ar One - ANO-1 & 2 'l Number 1, Nuclear Plant Road "]

Russellville,-AD 72801  !

Mr. Thomas W. Alexion i NRR Project Manager, Region IV/ANO-1 ,

U. S. Nuclear-Regulatory Comission NRR Mail Stop 11-B-19  :

One White Flint North' )

11555 Rockville Pike  :

Rockville, Maryland 20852 ]

Mr. Chester Poslusnv l NRR Project Mana,,er, Region IV/ANO-2 l U. S. Nuclear Regulatory Comission NRR Mail Stop 11-B-19 One White Flint North l 11555 Rockville Pike I Rockville, Maryland 20852 ,

Ms.. Greta Dicus, Director  !

. Division of Radiation Control and Emergency. Management .

Arkansas Department of Health 4815 West Markham Street.

Little Rock, AR 72201

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ARKANSAS NUCLEAR ONE, UNIT-2 STEAM GENERATOR TUBING INSERVICE INSPECTION REPORT 2R7 REFUELING OUTAGE INTRODUCTION 1

An inservice inspection was per formed on selected tubes in Steam Generators '

2E-24A and 2E-248 at Arkansas Nuclear One, Unit 2 during the period October 1-5, 1989. The number of steam generators inspected and the number of tubes in the initial sample for inspection in each steam generator were determined in accordance with ANO-2 Technical Specifications, Sections 4.4.5.1 and 4.4.5.2, respectively. The interval between this inspection  ;

(2R7) and the previous inspection (2R6, February 1988) is within the range of twelve to twenty-four calendar months required by the ANO-2 Technical Specifications in Section 4.4.5.3.

INSPECTION

SUMMARY

Tubes were inspected full length from the cold leg

• manway using Echoram

.590 inch bobbin coil probes at mixed (multi) frequencies of 400/100, 400/200, and 200/100 Khz. Probe withdrawal rates were 24 inches /second (ips), based on a successful demonstration of acceptable data at that  !

speed. In a few cases, it was necessary to retest at a probe speed of 12 l ips to obtain usable data in batwing areas. Zetec MIZ 18 systems were used for data acquisition.- DDA-4 analyzers were used for manual data interpretation and data management was done by the Westinghouse  ;

"Supertubin" system. .

An independent group provided secondary data analysis in parallel with the primary steam generator tubing ISI contractor.

The actual number of tubes inspected was 386 in 2E-24A (4.6%) and 396 in 2E-24B(4.7%). These numbers exceed the ANO-2 Technical Specification required minimum three percent. Tubes were selected both from special interest areas and on a random basis - areas of special interest are:

around the stay dome for two pitches (three tubes radially), the six tubes '

surrounding each of the seven tie rods, and tubes with previous .

indications.

• Since the location of the hot leg manway severely limits the reach of the eddy current fixture and because of ALARA considerations,'the tubes were probed from the ,old leg.

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~ INSPECTION RESULTS The results were in the C-1 category for both stemt generators i.e., there 1 were i.o defective tubes in either stet generator, and les', than five percent of the. total tubes inspected ex'ibited an/ degraddtion. /

1 In' steam generator 2E-24A, ten tubes had indications of less than 20% l through-wall; five. tubes had 20-29% through-wall indications; and three:  !

tubes had 30-39%' through-wall indications. Please note these totals irclude only the=1argest indication in each tube. Table 1 lists all l reportable indications, including multiple indications on the same tube,  ;

for steam generator 2E-24A. ,

In steam generator 2E-24B, six tubes had less than 20% through-wall indications; four tubes had 20-29% through-wall-indications; and seven tubes:had 30-39% through-wall indications. Again, these-totals include only the largest indications in each tube. Tabic 2 lists all reportable j indications in steam generator 2E-24B.

Minor dents were found in each steam generator, mostly at the tent.. or eleventh support plate in both hot and cold legs. There were a total of-143 tubes with dents in steam generator 2E-24A and 189 tubes in 2E-24B. J j

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. TABLE 1 l ARKANSAS NUCLEAR ONE - UNIT 2 i STEAM GENFRATOR 2E-24A  !

2R7 TUBE INoPECTION RESULTS

1. ' TUBES WITH INDICATIONS 20-39% OF WALL THICKNESS i

R0W- LINE INDICATION % LOCATION i t

38 130 23 TSH + 3.06".  :

36 32 22 TSH + 2.46" 82 64 31 TSH + 1.91" ,

39 .83 26 BW1 + 1.00" h 80 84 22 8H + 7.71"-

L 32 '96 20 BW3 + 0" ,

91 103 35 SH + 1.00"'

91 103' 21 SH + 20.23" 91 103 20 TSC + 1.72" 110 '134 33 BW1 - 0.96"  :

-2. TUBES WITH INDICATIONS LESS THAN 20% OF WALL THICKNESS .i R0W LINE INDICATION %. LOCATION lr 77 b, 11 8H + 19.82" E 32 70 13 TSC + 0.97" l

91 71 17~ TSH'+ 3.14" 40 74 16 TSC + 0.64" "

39 81 16 TSC + 1.40" 80 84 15 TSH + 4.02" 28 100- 18 TSC +.0.74" .

28 102 15 4H + 0.46" 91 '103 13 90 + 8.67"  !

31 105 12 5H + 30.33" )

-25 109 17 SH + 27.72" 36 110 12 TSH +-3.26" I

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TABLE 2 i ARKANSAS NUCLEAR ONE - UNIT 2 'i STEAM GENERATOR 2E-24B' I 2R7 TUBE INSPECTION RESULTS. 'i

1. TUBES WITH INDICATIONS 20-39% OF WALL THICKNESS R0W LINE INDICATION % LOCATION 92 22 21 BW1 + 0.94" '

i BW1 - 0.84" 97- 25 24 99 27 32 .BW5 - 0.91" 99 27 27 BW4 - 0.70" 103 29 31 BW5 + 0.99" 103 29 22 BW4 + 1.00" 37- 81 32 BW1 + 1.00"-

38 84 25 BW1 + 0.83" 42 84 32 BW5 + 0.97" 38 86 32 BW5 + 0.94" 77 89 27 TSH + 1.50" 34 94 33 BW1 - 0.91" i 34- 94 21 BW1 + 0.94" 33 95 3B 'BW1 - 1.06"- 1 33 95 27 DW5 + 0.97" 33 95 24 BW1 + 0.86" g

2. TUBES WITH INDICATIONS LESS THAN 20% OF WALL THICKNESS R0W LINE INDICATION % LOCATION' 92 22 18 BW4 - 1.00"  ;

96 24 -19 -BW5 + 0.99"-

96 24 10 BW4'+ 1.10f" 97 25 12 BWS + 1.00" 97 25 18 BW41- 0.73" 103 29 18 BW2 + 0.90" t 37 77 19 BW3 - 0.88" L 38 86 11 BW3 - 1~.00" L 38 86 17 BW5 - 1.00" i' 89 93 11 BW4 + 0.17" 102 96 11 TSH + 0.64" 29 99 19 BW5 + 0.89" t 29 -101 17 BW5 + 0.9P"

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