ML20082U623

Special Rept SR-91-003-01:on 910406,inservice Eddy Current Exam of Facility SG Tubing Completed by Westinghouse.Rept Submitted Per Tech Specs 4.4.4.5 & 6.9.2.Rotating Pancake Coil Exam Results Verified No Detectable Degradation

ML20082U623
Person / Time
Site:	Waterford
Issue date:	09/16/1991
From:	Packer D ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SR-91-003-01, SR-91-3-1, W3B5-91-0237, W3B5-91-237, NUDOCS 9109200268
Download: ML20082U623 (18)

Text

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Operations W3HL-91 0237 A4.05 QA September 16, 1991 U.S. Nuclear Regulatory Commission ATTENTION:

Document Control Desk Washington, D.C.

20555

SUBJECT:

Waterford 3 SES Docket No. 50-382 LicensJ No. NPF-38 Reporting of Special Report Gentlemen:

Attached is Special Report Number SR-91-003 01 for Waterford Steam Electric Station Unit 3.

This Special Report is submitted per Technical Specifications 4.4.4.5 and 6.9.2.

Very truly your,

/

Cm k O/,f..

'I D.F. Packer General Manager Plant Operations DfP/WEF/rk Attachment cc:

Messrs. R.D. Martin G.L. Florreich J.T. Wheelock INPO Records Center E.L. Blake N.S. Reynolds NRC Resident inspectors Office l

100C04

-9109200269 910916 PDR ADOCK 050003B2

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l S

PDR

l SPECIAL REPORT SR-91-003-01 STEAM GENEPATOR EDDY CpHRENT EXAMINATION (ATH KEFUEl.ING)

INTRODUCTION Inservice eddy current examination of Waterford 2 Steam Generator (SG) tubing was completed by Westinghouse Electric poration NSD on April 6, 1991.

This report is submitted in accordance with Technical Specification 4.4.4.5, which requires the con.plete results of this inspection be submit ted in a special report pursuant to Technical Specification 6.9.2, within 12 n'on;hs f ollowing the inspection.

The eddy current testing included full length bobbin coil examinations of 318 tubes (3.4%) In SG #1, and 303 tubes (3.2%) in SG #2.

Additionally, 259 tubes (2.7%) in SG #2's hot leg were examined at the top of the tubesheet with a Rotating pancake Coll (EPC) to inapect for circumferential cracking induced by stress corrosion cracking. RpC examination resulta verified No Detectable Degradation (NDD).

As recommende1 by Combustion Engineering's Report CEN-328, " Remedy Ior Steam Generator Tube And Diagonal Strap Wear," Waterford 3 elected to plug the remaining tubes in the batwirg uear concern area. A total of 312 tubes (156 tubes per SG) were plugged with bestinghouse Inconel-690 mechanical plugs as part of batwing preventive plugging.

Prior to any plugging, Westinghouse identified nnd marked tubes to be plugged by utilizing the Eddy Current Test (ECT) probe to ensure correct hot / cold leg tubcsheet locations.

Steam generator tubesheet marking was performei in accordance with Plant approved Westinghouse procedure MRS 2.2.2 GEN-12, Rev. 2, "Ste n Generator Tubesheet Marking."

Additionally, Waterford 3 deelded to have '4cstinghouse remove 6 Inconel-600 mechanical plugs (3 per hot leg) which were subject to Primary Water Stress Corrosion Cracking (PWSCC).

During tube plugging activities, Westinghouse reinstalled 6 Inconel-690 mechanical plugs of Heat No. NX-6779HK.

1

l All SG tube examinations were conducted in accordance with USNRC Hegulatory Guide 1.83 and ASME Section XI using Westinghouse procedure MRS 2.4.2 GEN-28

" Digital Multifrequency Eddy Current inspection of Preservice And Innervice Heat Exchanger Tubing."

i HESULTS OF E'.(AMINATION S1EAM CENERATOR #1 The eddy current testing of 318 tubes in SC #1 resulted in the following analysis of 32 indications!

o 6 Tubes Greater Than or Equal To 20% Thru Wall But Less Than 40% Thru

-Wall F

o 7 Tubes Lens Than 20% Thru Wall o 19 Tuben With Manufacturing Buff Marks (MBMs)

In addition, a video scan of SG #1's tubesheet was perfortned to verify plugged tube locations. All tube plugs in SG #1 were secure and in the correct tube locations.

f The following tube listing identifies the indicaticun as a result of examining.

-318 tubes (3.4%) in SG #11 1.

ROW LINE

% THRU WALL LOCATION COMMENTS 28 18 MhM BW1 15' 25 20%

6H 37 33 MBM TSil 70 38 MBM TSC 1

l

.. m

S, TEAM CENERATOR #1 (Cont 'd) r R0W LINE

% TilRtf WALL LOCATION COMMENTS l

137

'57 MBM TSC 19-67 29%

BW5 PLUCCED (PREVENTIVE.

i PLUGGING) 56 TO MBM 6 11 j

2 96

.76 MBM IC i

95 77

- MBM 5C/70 54 78 MBM 4C 74 76 MBM 2C/SC 146 80 19%

BW1

- I 82 86 19%

BW9 83 87 ~

MBM 41I 80 88 MBM 80 i

f l-104 88 MBM 6C/711 l

l 53 91 MBM 7c 147 91

- 12%

BW9 l

84 92 11%

7C

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FWe yW ' e' t W y 4M 4t"e-e -Y ve + 5+=NP+

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STEAM GENERATOP #1, (Cont'd)

ROW LINE

% TI:RU WAL1, LOCATION COMMENTS j

145 95 11%

BW9 146 96 12%

BW9 146 100 121 Et'9 75 105 26%

4 11 PLUGGED (PHEVENTIVE PLUGGING) 46 106 MBH 6C 82 108 MhH 2 11 j

77 113 MBM-6C/811 136 120 MBM BW1 30

'126 MBM TSC 70 134

-32%/34%

BW4/BW5 Pl.UGGED (PREVENTIVE

- PLUGGING) 46 148 36%

BWS Pl.UGGED PREVENTIVE PLUGGINC)

- 2 2 --

158

.MBM _

SC 32 158-20%

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STEAM GENERATOP #1 (Cont'd) i l

The following list of SG #1 tubes were plugged Refuel 4 as a result of Combust'on Engineering's recommendation for resolving the batwing wear area concernt ROW-LINE RDW

!.INE l

l 30 70 35 71 I

32 70 37 71 34 70 39-71 36 70 41 71 38 10 43.

71

}'

40 70 32 72 42 70 34 72 I

31 71' 36

~72 i

33

.71 38 72 k

i 40 72 48 76 l

l E42 72.

41 77 I

f t

44 72.

43 77.

1

-f 33 73 45 77

-j f

37 73 47 77 t

i b

l rn

STEAM GENERATOR #1 (Cont'd)

ROW 1.1 NE HOW 1,1 N E 39 73 44 78 41 73 46 78 43 73 48 78 45 73 43 79 34-74 45 79 36 74 47 79 38 74 46 80 40-74 48 80 42-74 50 80 44 74 47-81 t

46 74 49 81

-37 75-51 81 I

t 39 75 48 82 41-75 50 82

+

43 75-52 82 45 75 47 83 i

6 e

.--_-.i2 1_ i-.___.__.__,

STEAM CENERATOR #1 (Cotit ' d)

ROW LINE BOW 1.1 N E 47 75 51 83 38 76 48 84 40 76 50 84 42 76 52 84 46 76 49 85 51 85 47 95 53 35 49 95 48 86 51 95 50 86 46 96 52 86 48 96 49 87 50 96 48 8"

45 97 50 88 47 97 52 88 42 98 49 89 44 98 51 89 46 98

STEAM GENERATO'.< #1 (Cont'd)

R 0k' LINE F 0b' LINE 48 90 48 98 50 90 43 99 52 90 45 99 49 91 47 99 51 91 40 100

$3 91 42 100 48 92 44 100 50 92 46 100 52 92 48 100 47 93 39 101 49 93 41 101 51 93 43 101 48 94 45 101 50 94 47 101 52 94 34 102 36 102 40 104

______..____._m

_.-__m__

4

, STEAM GENERATOR til (Cont'd)

EDW LINE

,R, O'd LINE 38 102 42 104 40 102 44 104 42 102 31 105 44 102 33 105 46 102 35 105 33 103 37 105 35 103 39 105 37 103 41 105 39 103 43 105 41 103 30 106 43 103 32 106 i

45 103 34 106 32 104 36 106 34 104 38 106 36 104 40 106 38 104 42 106

!I j

j I

t STEAM CENERATOR #1-i i

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In addition, the following SG #1 hot leg tube mechanical plugo (inconel-600)

. ere retraved and replaced with Inconel-690 mechanical plugst I

w HOW l.INE s

s

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12 *.

45 I

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42 78 l

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49 83 4

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STEAM GENERATOR #2, i

The Eddy Curre.it Testing of 303 tubes in SG #2 resulted in the following l

analysis of 15 indientions:

o 5 Tubes Greater Than 20% Thru Wall But Lens Than 40% Thru Wall t

o 2 Tubes Less Than 20% Thru Wall o 8 Tubes W1th Manuf acturing Buf f Mm ks (M11Ms)

In addition, a video scan of SG #2's tubesheet was performed to verify plugged tube Ic ations. All tube plugs in SG #2 were secure and in the correct tube locationn.

t The following tube listing identifies the indiention as a result of examining 303 tubes (3.2%) in SG #2:

30W LINE I TilRU WALL 1.0 CATION COMMENTS f-

.21 16%

IC

.' 0 5 31 12%

5 11 l

22 44 MBM 1 11 30 46 MEM lit 137.-

57 26%

llW1 PLUGGED (PREVENTIVE PLUGGING) 17 67 37%

P,W1 PLUGGED (PREVENTIVE PLUGGING) 146 86

~

26%

BW9 PLUGGED (PREVENTIVE PLUGGING) l l

l

~

STrfM GENERATOR #2 (Cont'd)

ROW LINE i TilRU UA1.L LOCAT'.CN COMMENTS 66 88 35%

BW4 PLUGGEJ (PREVENTIVE PLUGGING) 91 89 MBM 14'7 145 91 30%

BW8 PLUGGED (PREVENTIVE Pl.UGGING) 128 102 MBM 7C 75 111 MBM 2C 39 113 MBM IH 2

114 MBM 3C 138 114 MBM TSil The followinr. list of SG #2 tubes were plugged Refuel 4 at a result of Combustion Engineering's recommendation for resolving the batwing wear area concern:

ROW LINE ROW LINE 30 70 42 72 22 70 44 72 34 70 35 73 36 70 37 73

)

STEAM CENERATOR f2, (Cont'd) i RW LINE-ROW 1.l N E 1

i 38 70 39 73 40-70 41 73 42 70 43 73 31 71 45 73

-33 71-34 74

'35 71 36 74 37 71 38 74 P

39

~71 40 74 41 71 42 74 43

-71 44 74 32 72 46 74 34 72 37 75 36

.72 39 75

Y 38:

7_2 41 75.

40 72 4)

-75~

43 75 47-83 j

n.

3

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+. -

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_ _ _ = _

1 i

STEAM CENERATOR #2 (Cont'd)

]

ROW LINE R0W LINE ll 47 75 49 83 I

38 76 51 83 i

i-42 76-48 84 44 76 50 84 3

/6 76 52 84-1

- 48 76 49 85 I

i 41 77 51 85 i

i l

43 77 53 85

. t 45' 77 48 86 41 77 50 86 42 78 52 86

~44,

-78 49 87 46 78 51-87 48 78 48 88 43 79.

50 88 i.

45 79-52 88 eewh=--

+ E n.-

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.. -.- -.~. -.. -. -.... - - -

4 STEAM CENEHg DR #2 (Cont'd)

-i ROW LINE ROW LINE 47 79 31 89 j

i 46 83 48 90 l

48 80

$0 90 I

$0 80-52 90 49 81 49 91 51 --

81 51 91 48 82

$3 91

$0 82 48 92 e

52 81 50 92 s2 92 48 100 r

47 93 37 101 t

'49 93 39 101 51 93 41 101 48 94

.43 101 1

50 94 45' 101.

4 52 94 47 101

-. -..,,, -. - ~,- -,. -

STEAM CENERATOR #2 (Cont'd)

ROW L1]E EDW LINIl 49 95 34 102 51 95 38 102 46 96 40 102 48 96 42 102 50 96 44 102 43 97 46 102 45 97 35 103 47 97 37 103 42 98 39 103 44 98 41 103 46 98 43 103 48 98 45 103 c

41 99 32 104 43 99 34 104 47 99 36 104 38 100 38 104

STI AM Cl:NERNIDit #2 (Cont'd) 14 OW i.1 N E ItOW L1NF 42 100 40 104 44 100 42 104 46 100 44 104 31 105 30 106 33 105 33 106 35 105 34 10f.

37 105 36 106 39 105 38 106 41 105 40 106 43 105 42 106 The following list of SG #' hot Icg tube mechanical plugs (Inconel-600) were removed and replaced with Inconel--690:

It0W LINE

'3 73 47 95 19 109 Plant Contact J.E. Iloward. Prcourement/ Programs Engineering Manager (504)739-6327

. _ _ _ _ _ - _ _