ML20137W729
| ML20137W729 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/20/1985 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| SPR-85-012, SPR-85-12, NUDOCS 8510040376 | |
| Download: ML20137W729 (6) | |
Text
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s SOUTH CAROLINA ELECTRIC & GAS COMPANY POST OFFICE 764 COLuusiA. south CAROLINA 29218 September 20, 1985 o w.o.O. a d'lls'AL.
En SEP 23 A 9 : 23 Dr. J. Nelson Grace Regional Administrator U.' S. Nuclear Regulatory Commission Sulte 2900 101 Marietta StreeC, NW Atlanta, Georgia 30323 l
SUBJECT:
Virgil C. Summer Nuclear Station j
Docket No. 50/395 Operating License No. NPF-12 Special Report (SPR 85-012)
Steam Generator Tube Eddy Current Examination
Dear Dr. Grace:
This report is being submitted in accordance with Technical Specification 4.4.5.5(b).
As previously stated in Special Report (SPR)84-016, dated November 14, 1984, this inspection constitutes the "First Inservice Inspection" of steam generator tubes as required by Technical Specifications 4.4.5.2 and 4.4.5.3 The identification of tubes plugged as required by Technical Specification 4.4.5.5(a) was previously reported in SPR 84-016 and the 1984 Annual Report.
This report includes:
1.
Introduction 2.
The number and extent of tubes inspected 3
Location and percent of wall thickness penetration for each indication of an imperfection 4.
Identification of tubes plugged Should there be any questions, please call us at your convenience.
Very truly yo
. g O. W. Dixon, Jr.
CJM:0WD/ led Attachment cc:
(See Page Two) 8510040376 850920 DR ADOCK O y5
- Sl xEA9
Dr. J. Nelson Grace SPR 85-012 Page Two September 20, 1985 cc:
V. C. Summer J. A. Warren T.
C. Nichols, Jr./0. W. Dixon, Jr.
E. H. Crews, Jr.
E. C. Roberts W. A. Williams, Jr.
D. A. Nauman Group Managers
- 0. S. Bradham C. A.
Price S.
R. Hunt D. A. Lavigne J. F. Heilman C. L. Ligon (NSRC)
K.
E. Nodland R. A. Stough G. Percival C. W. Hehl J. B. Knotts, Jr.
S. D. Hogge I&E Washington Document Management Branch INPO Records Center ANI Library NPCF File
Dr. J. Nelson Grace SPR 85-012 Page Three September 20, 1985 STEAM GENERATOR A, B, &C OCTOBER 1984 INTRODUCTION STEAM GENERATOR TUBE EDDY CURRENT EXAMINATION The first inservice eddy current examination of the Virgil C.
Summer Nuclear Station steam generator tubing was performed during the month of October 1984.
This examination was performed in accordance with the ASME " Boiler and Pressure Vessel Code"Section XI, 1974 edition, 1975 addenda and the 1977 edition of Section XI through Summer 1978 addenda and as specified by the Nuclear Regulatory Commission, Regulatory Guide 1.83, Revision 1, dated July 1975.
The following basic program was used for each steam generator: 100 percent of rows 44, 45, 46, 47, 48 and 49, a 7 x 4 matrix of the remainder of the steam generator tubes, all peripheral tubes including row 1 and 10 percent of row 2.
Inspection was conducted from the inlet side (Hot Leg) for Full Length (F/L) of tubes and to the 14th support (14C) outlet side (Cold Leg) for small radius U-bends.
The examination was conducted utilizing the multifrequency eddy current technique.
In the "A"
steam generator one tube was plugged, row 1 column 1,
for a 37 percent through wall indication in the hot leg tube sheet.
This indication was 18.3 inches from the tube end and appears to have originated from the inside diameter of the tub e.
Pre-service baseline data was reviewed and no indication was present at that time.
Three tubes in the pre-heater section showed minor wear indications less than 20 percent through wall.
In the "B"
steam generator two tubes were plugged.
How 1 column 107 had a 100 percent through wall indication at the hot leg tangent of the U-bend.
Row 1 column 60 had a 97 percent through wall indication in the hot leg tube sheet 20.4 inches from the tube end.
Pre-service baseline data was reviewed on both tubes and no discontinuity indications were present.
Thirteen tubes had minor wear indications in the pre-heater section less than 20 percent through wall.
In the "C"
steam generator one tube, row 1 column 42, was plugged for a 99 percent through wall indication in the hot leg tube sheet 18.7 inches from the tube end.
Pre-service baseline data was reviewed and no indication was present.
Eight tubes in the pre-heater section showed minor wear indications at the support plates less than 20 percent through wall.
-... =. _..
i 1
Dr. J. Nelson Grace i
SPR 85-012 Page Four September 20, 1985 1
EXAMINATION RESULTS The following is a. tabulation of the number and extent of tubes inspected, the location and percent of wall thickness penetration for each indication and the identification of the tubes plugged.
STEAM GENERATOR:
A 4
TUBES INSPECTED THIS OUTAGE i
EXIENT NUMBER F/L 622 i
14C 128 l
TOTAL 750 t
d TUBES WITH INDICATIONS ROW COL LEG EXTENT LOCA'. ON VOLTS DEG 49 40 H
F/L 14C+ " 0.0 1.51 140
<20 l
48 43 H
F/L TEH-20.0 6.66 158
<20 47-48 H
F/L
- 12C,
.76.4 0.77 153 23 47 72 H
F/L 12C+
27.,
0.9?
159
<20 1
48 73 H
F/L 13H+
16.0 1.39 169
<20 48 75 H
F/L 06C+
0.0
' 54 0
<20 49 75 H
F/L 06C+
0.0 0.'0 0
<20 49 76 H
F/L 06C+
20.0 0.3.
O
<20 48-77 H
F/L 06C+
0.0 0.21 0
<20
- 1 1
H 14C TEH+
18.3 37.73 21 37 i
i i
NUMBER OF TUBES WITH INDICATIONS:
10 I
- IUBES PLUGGED THIS OUTAGE i
1 NOTE:
TEH = TUBE END HOT (MEASUREMENT TAKEN FROM POINT OF ENTT:
HOT LEG).
l I
I
+
J
Dr. J. Nelson Grace SPR 85-012 Page Five September 20, 1985 STEAM GENERATOR:
B TUBES INSPECTED THIS OUTAGE EXTENT NUMBER F/L 636 14C 135 TOTAL 771 TUBES WITH INDICATIONS ROW COL LEG EXTENT LOCATION VOLTS DEG 18 10 H
F/L 11H+
28.2 0.56 146
<20 29 18 H
F/L 05H+
5.6 0.93 153
<20 30 18 H
F/L 08H+
6.0 1.04 160
<20 18 20 H
F/L 08H+
20.1 2.07 171
<20 49 31 H
F/L TEH+
3.7 13.90 160
<20 H
F/L TEH+
19.2 15.35 161
<20 48 47 H
F/L 07C+
0.0 0.25 0
<20 9
50 H
F/L 11H+
20.0 1.52 164
<20 2
52 H
14C 05H+
36.4 1.54 160
<20 48 55 H
F/L 06C+
0.0 0.40 0
<20 32 60 H
F/L 01C+
2.8 0.99 155 22 H
F/L 01C+
2.8 0.56 150 24 48 64 H
F/L 06C+
0.0 0.39 0
<20 49 64 H
F/L 06C+
0.0 0.43 0
<20 48 69 H
F/L 06C+
0.0 0 38 0
<20 49 70 H
F/L 06C+
0.0 0.25 0
<20 47 72 H
F/L 08C+
0.0 0.26 0
<20 H
F/L 06C+
0.0 0.37 0
<20 48 72 H
F/L 06C+
0.0 0.30 0
<20 29 75 H
F/L 11C+
9.7 1.06 170
<20 48 75 H
F/L 06C+
0.0 0.26 0
<20 49 75 H
F/L 08C+
0.0 0.17 0
<20 48 76 H
F/L 06C+
0.0 0.35 0
<20 46 77 H
F/L 07C+
0.0 0.46 0
<20 49 77 H
F/L 06C+
0.0 0.18 0
<20
- 1 60 H
14H TEH+
20.4 47.75 44 97 H
14C TEH+
20.4 48.42 43 98
- 1 107 H
F/L 14H+
2.4 28.61 17 100 H
14C 14H+
2.4 5.07 29 100 NUMBER OF TUBES WITH INDICATIONS:
24
- TUBES PLUGGED THIS OUTAGE
Dr. J. Nelson Grace SPR 85-012 Page Six September 20, 1985 STEAM GENERATOR:
C TUBES INSPECTED THIS OUTAGE EXTENT NUMBER F/L 633 14C 129 TOTAL 762 TUBES WITH INDICATIONS ROW COL LEG EXTENT LOCATION VOLTS DEG 4
5 30 H
F/L TEH+
13.2 26.46 164
<20 47 36 H
F/L 08H+
17.8 1.29 150
<20 H
F/L 08H+
17.8 1.29 150
<20 48 56 H
F/L 06C+
0.0 0.38 0
<20 49 56 H
F/L 06C+
0.0 0.27 0
<20 48 58 H
F/L 08C+
0.0 0.27 0
<20 49 58 H
F/L 06C+
0.0 0.27 0
<20 49 60 H
F/L 06C+
0.0 0.31 0
<20 49 62 H
F/L 08C+
0.0 0.34 0
<20 48 64 H
F/L 06C+
0.0 0.24 0
<20
- 1 42 H
14H TEH+
18.7 20.64 28 84 H
14C TEH+
18.7 23.89 33 99 NUMBER OF TUBES WITH INDICATIONS:
10
- TUBES PLUGGED THIS OUTAGE c
. - _ _.