ML20073H070
| ML20073H070 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/29/1994 |
| From: | Blosser J UNION ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20073H073 | List: |
| References | |
| ULNRC-03080, ULNRC-3080, NUDOCS 9410050108 | |
| Download: ML20073H070 (15) | |
Text
j Ca!!away Plant j
Post Othce B3 E20 Fu!!an. M ssouri 65261 Uvrou Eizernic September 29,1994 EE U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 ULNRC-03080 Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT I FACILITY OPERATING LICENSE NPF-30 SPECIAL REPORT 93-03 (SOS 93-1622)
RESULTS OF TIIE SIXTII STEAM GENERATOR TUBE INSERVICE INSPECTION REF: ULNRC-2904, dated 11/S/93 The enclosed Special Report is submitted pursuant to the requirements of Callaway Technical Specification 4.4.5.5.b concerning the seventh inservice Eddy Current Inspection of Steam Generators 'A' and 'D' performed in October 1993, during Callaway Plant's sixth refueling outage. This report documents the final Conam inspection results.
. D. Blosser Manager, Callaway Plant JDB/HDB/MAH /lrj Enclosure I
cc: Distribution attached 1
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Mr. J. B. Martin Regional Administrator U. S. Nuclear Regulatory Commission Region ill 801 Warrenville Road Lisle, Illinois 60532-4351 Mr. L. Raynard Wharton (2 copies) 1 Licensing Project Manager U. S. Nuclear Regulatory Commission OWFN - Mail Stop 13E21 Washington, D. C. 20555 Manager, Electric Department Missouri Public Service Commission P. O. Box 360 Jefferson City, MO 65102 Records Center Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339 i
Mr. Steve Wideman Supervisor, Licensing i
Wolf Creek Nuclear Operating Corporation P. O. Box 411 Burlington, K7 36839 Mr. M. J. Farber Chief, Reactor ProjectsSection III A
(
U. S. Nuclear Regulatory Commission Region III 801 Warrenville Road Lisle, Illinois 60532-4351 Mr. Thomas A. Baxter Shaw, Pittman, Potts & Trowbridge 2300 N. Street N.W.
Washington, D.C. 20037 NRC Senior Resident Inspector i
SPECIAL REPORT 93-03 RESULTS OF SEVENTH STEAM GENERATOR TUBE INSERVICE INSPECTION i
This report is submitted in accordance with Technical Speci0 cation (T/S) 4.4.5.5.b, which states:
"The complete results of the steam generator tube inservice inspection shall be l
submitted to the Commission in a Special Report pursuant to Specification 6.9.2 i
within 12 months following the completion of the inspection.
This Special Report shall include:
(1) Number and extent of tubes inspected, I
(2) Location and percent of wall-thickness penetration for each indication of an i
imperfection, and (3) Identification of tubes plugged."
In October 1993, with the plant in Mode 6 - Refueling for the sixth refueling outage, the seventh plant Steam Generator (S/G) Eddy Current Inservice Inspection was performed. S/G's 'A' and 'D' were inspected. The inspection was performed by Conam Nuclear, Inc., and their formal results are detailed in the Eddy Current Examination (ECE) which is submitted with this Special Report.
Although the Conam ECE provides details on the inspection, the results are summarized below and are numbered to correspond with the information requested by T/S 4.4.5.5.b:
(1) Number / Extent of Inspected Tubes (a)
Inspection Summary:
S/G ' A' S/G 'D'
-l Tubes Plugged (Refuel 6) 19 18 Tubes Previously Plugged 12 10 i
I Total Tubes Plugged 36 48 i
f Page1 j
1
.-=
h Page 2 SPECIAL REPORT 93-03 l
S/G ' A' S/G 'D' Tubes evaluated with 5609 5596 standard bobbin coil Tubes plugged previously 17
_)3 Total Tubes 5626 5626 Tubes further evaluated with MRPC probes:
STEAM GENERATOR 'A':
STE4M GENERATOR 'D':
07C-06C 5
06H-07H I
06H-0711 4
07C-06C 1
1 0311-04H 1
05C-04C 2
04C-03C 3
04H-05H I
01H-02H 4
05H-0611 2
02H-03H 1
02C-01Cc 3
04H-05H I
03C-02C 3
05C-04C 1
02H-0311 2
I 02C-01C 1
06C-05C 1
03C-02C 1
04C-03C 2
TSH-OlH I
OlH-02H 1
OIC-TSC 1
OlC-TSC 1
OIC-FBC 1
TSH-FBH I
05H-0511 2
FBC-TSC 1
l TSH-TSH 126 FBH-OlH I
l TSC-TSC 64 TSH-TSH 482 03C-03C 4
07H-07H 2
07H-07H 3
OlH-01H 1
02H-02H 3
04H-04H 1
03H-0311 1
02H-0211 2
05C-05C 2
04C-04C 1
OlH-OlH I
01C-01C 2
02C-02C 4
03H-03H 1
04H-04H 1
06C-06C 2
04C-04C 1
06H-06H I
SUBTOTAL 226 SUBTOTAL 512
Page 3 SPECIAL REPORT 93-03 (b) Steam Generator 'A' One hundred percent of the unplugged tubes or five thousand six hundred nine (5609) tubes were tested full length using the standard bobbin coil probe. In addition to the bobbin probe examination,126 inlet leg tube sheet interfaces were examinea Ng a three-coil MRPC (motorized rotating pancake coil) probe. Thi.
be utilizes one pancake coil, one coil sensitive to axial indications and one coil sensitive to circumferential indications. There were no indications -
reproted at the inlet tube sheet interface.
I During this outage, there were nineteen (19) tubes plugged in Steam j
Generator 'A'. Fourteen (14) tubes removed from service for indications at anti-vibration bars AVB...five (5) for indications greater than 48 percent through wall and nine (9) tubes for indications from l
between 35 and 47 percent through wall. The other five (5) tubes l
were plugged due to possible wall thinning from a foreign object lodged outside the tubes. A Foreign Object Search and Retrieval (FOSAR) was performed to locate and remove the foreign object.
The foreign object was later determined to be weld slag.
l (c) Steam Generator 'D':
One hundred percent of the unplugged tubes or five thousand five j
hundred ninety-six (5596) tubes were tested full length using the bobbin coil probe. In addition to the bobbin probe examination, 482 inlet tube sheet interfaces were examined with a three-coil MRPC probe. There were no indications reported at the inlet tube sheet j
interface. There were 18 tubes removed from service for indications at AVB. Three (3) tubes were removed from service for indications l
greater than 48 percent through wall. The other 15 tubes had indications from between 35 and 47 percent through wall.
l (2) Location / Percent of Wall-Thickness Penetration for Each Indication of Imperfeetion
{
See Tables 1 and 2 l
(Percent of wall-thickness penetrations are shown for indications of
__ 20 %.)
i
l Page 4 SPECIAL REPORT 93-03 (3) Identification of Tubes Plugged from the Seventh Inservice inspection -
All tubes plugged in the seventh inservice inspection used In:onel 690 plugs.
STEAM GENERATOR ' A' STEAM GENERATOR 'D' ROW COLUMN
% INDI-ROW COLUMN
% INDI-CATION CATION 39 16 41 29 9
35 41 18 41 39 17 36 52 32 DTl/LP 43 24 48 52 34 60 48 25 42 56 45 DTl/LP 47 27 35 57 45 SUl/LP 44 28 38 46 46 36 47 33 37 55 46 DTl/LP 46 39 54 i
56 46 LP 13 59 NQI 42 47 38 52 65 48 46 47 40 52 66 43 47 53 41 50 83 46 51 59 55 47 84 34 54 60 52 49 90 40 51 61 39 48 92 38 46 88 35 48 93 40 46 90 49 36 110 45 42 96 38 33 112 40 46 96 43
Page 5 SPECIAL REPORT 93-03 DEFINITIONSJ DTI - Distorted Top of Tubesheet with Indication.
SUI - Single Volumetric Indication.
NQI - Non-Quantifiable Indication.
LP - Loose Part.
KEY - TAllLES 1 AND 2 AV1,2,3,4,5,6 - Anti-Vibration Bars 0211,0711,07C, etc. - Tube Support Plate Numbers / Cold Leg (C), Hot Leg (H)
TSII - Tubesheet Hot
i SPECIAL REPORT TABLE 1 TUBE IMPERFECTIONS - STEAM GENERATOR 'A' INDICATION %
INCH (+) FROM I
ROW COLUMN NALL THINNING LOCATION LOCATION 31 11 21 AV5 0.00 l
32 11 20 AV2 0.00 l
33 11 35 AV2 0.00 33 11 22 AV5 0.00 32 12 30 AV3 0.00 36 13 30 AV4 0.00 39 16 41 AV4 0.00 35 17 26 AV4 0.00 39 18 23 AV3 0.00 39 18 23 AV4 0.00 39 18 22 AV6 0.00 41 18 36 AV2 0.00 41 18 41 AV4 0.00 41 18 32 AV6 0.00 35 20 27 AV3 0.00 32 22 26 AV2 0.00 36 23 20 AV4 0.00 t
43 27 24 AV2 0.00
[
46 29 31 AV4 0.00 46 29 25 AVS 0.00 39 30 21 AV3 0.00 i
39 30 21 AV4 0.00 39 34 26 AV3 0.00 39 34 36 AV4 0.00 t
52 34 60 AV2 0.00 j
52 34 25 AV3 0.00 52 34 42 AV4 0.00 i
3 52 34 52 AV5 0.00
+
52 34 35 AV6 0.00 53 34 26 AVS 0.00
}
53 34 36 AV6 0.00 Page 1 of 4 l
I
i
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SPECIAL REPORT TABLE 1 TUBE IMPERFECTIONS - STEAM GENERATOR 'A' INDICATION %
INCH (+) FROM ROW COLUMN NALL THINNING LOCATION LOCATION 47 38 23 AV3 0.00 47 38 31 AV5 0.00 42 40 26 AV4 C.")0 42 46 35 AV3 0.00 46 46 25 AV2 0.00 46 46 36 AV3 0.00 46 46 30 AV4 0.00 35 47 25 AV2 0.00 35 47 33 AV4 0.00 35 47 24 AV5 0.00 42 47 38 AV3 0.00 42 47 22 AV4 0.00 46 47 40 AV3 0.00 26 48 25 AV5 0.00 32 48 20 AV3 0.00 32 48 20 AV4 0.00 46 48 25 AV3 0.00 46 48 32 AV4 0.00 47 53 20 AV2 0.00 47 53 30 AV3 0.00 47 53 41 AV4 0.00 47 55 25 AV2 0.00 47 57 30 AV4 0.00 47 59 28 AV3 0.00 47 59 27 AV5 0.00 51 59 40 AV2 0.00 51 59 49 AV3 0.00 51 59 55 AV4 0.00 51 59 21 AVS 0.00 54 60 50 AV3 0.00 54 64 52 AV4 0.00 54 60 52 AV5 0.00 54 60 23 AVB 0.00 i
Page 2 of 4
SPECIAL REPORT TABLE 1 TUBE IMPERFECTIONS - STEAM GENERATOR 'A' INDICATION %
INCH (+) FROM i
ROW COLUMN NALL THINNING LOCATION LOCATION l
41 61 21 AV3 0.00 41 61 27 AV4 0.00 51 61 31 AV1 0.00 51 61 28 AV2 0.00 51 61 39 AV3 0.00 51 61 23 AV4 0.00 51 61 25 AV6 0.00 53 64 24 AVS 0.00 53 64 30 AV6 0.00 46 65 20 AV5 0.00 46 67 29 AV4 0.00 32 78 24 AV6 0.00 50 79 23 AV3 0.00 50 79 22 AV4 0.00 46 83 20 AV3 0.00 39 86 26 AV4 0.00 46 88 35 AV2 0.00 46 88 29 AV3 0.00 46 88 26 AV4 0.00 46 88 25 AV5 0.00 46 90 49 AV4 0.00
{
39 92 20 AV4 0.00 42 94 22 AV3 0.00 42 94 23 AV5 0.00 i
42 96 35 AV2 0.00 42 96 38 AV3 0.00 42 96 21 AV5 0.00 46 96 31 AV2 0.00 46 96 43 AV5 0.00 j
42 97 20 AV5 0.00 i
Page 3 of 4 e
6 SPECIAL REPORT TABLE 1 TUBE IMPERFECTIONS - STEAM GENERATOR 'A' INDICATION %
INCH (+) FROM ROW COLUMN NALL THINNING LOCATION LOCATION 39 100 30 AV3 0.00 33 111 28 AV3 0.00 33 111 27 AV5 0.00 32 112 27 AV2 0.00 29 114 22 AV2 0.00 29 114 21 AV6 0.00 i
i I
l Page 4 of 4 l
SPECIAL REPORT TABLE 1 TUBE IMPERFECTIONS - STEAM GENERATOR 'D' INDICATION %
INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION 27 8
25 AV1 0.00 28 8
20 AVG 0.00 29 9
35 AV5 0.00 31 10 32 AV2 0.00 31 10 21 AV5 0.00 31 12 21 AV2 0.00 34 14 28 AV3 0.00 34 14 26 AV4 0.00 35 16 34 AV3 0.00 35 17 29 AV3 0.00 19 17 36 AV3 0.00 39 17 36
'AV4 0.00 40 23 30 AV5 0.00 41 23 30 AV3 0.00 41 23 30 AV4 0.00 l
i 40 24 21 AV4 0.00 40 24 21 AV5 0.00 43 24 48 AV4 0.00 43 25 23 AV2 0.00 43 25 25 AV4 0.00 43 25 31 AV5 0.00 48 25 42 AV4 0.00 41 26 26 AV4 0.00 47 27 28 AV3 0.00 47 27 35 AV5 0.00 44 28 28 AV2 0.00 44 28 38 AV3 0.00 44 28 22 AV4 0.00 45 28 27 AV2 0.00 45 28 21 AV4 0.00 Page 1 of 4
i
.l i'
SPECIAL REPORT l
TABLE 1 TUBE IMPERFECTIONS - STEAM GENERATOR 'D'
(
l INDICATION %
INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION l
i f
45 28 21 AVS 0.00 41 29 33 AV4 0.00 j
47 33 28 AV3 0.00 47 33 37 AV5 0.00 47 34 25 AV2 0.00 47 34 32 AV4 0.00 s
47 34 29 AV5 0.00 46 39 25 AV3 0.00 l
46 39 54 AV4 0.00 l
46 39 25 AV5 0.00 48 42 26 AV4 0.00 47 43 30 AV4 0.00 47 43 24 AV5 0.00 37 44 20 AV3 0.00 47 44 23 AV3 0.00 47 44 27 AV4 0.00 47 44 26 AV5 0.00 51 47 30 AV2 0.00 46 50 27 AV3 0.00 46 50 24 AV4 0.00 52 65 48 AV2 0.00 52 65 40 AV3 0.00 i
52 65 41 AV4 0.00 52 65 21 AV5 0.00 52 66 43 AV2 0.00 52 66 38 AV3 0.00 52 66 34 AV4 0.00 16 68 23 03H 31.49 52 68 28 AV2 0.00 52 68 31 AV3 0.00 Page 2 of 4 i
i SPECIAL REPORT TABLE 1 I
TUBE IMPERFECTIONS - STEAM GENERATOR 'D' I
l INDICATION %
INCH ( + ) FROM l
ROW COLUMN WALL THINNING LOCATION LOCATION 52 68 28 AV5 0.00 i
37 72 27 AV4 0.00 t
52 73 25 AV2 0.00 52 73 28 AV3 0.00 52 73 23 AV4 0.00 i
i 46 81 23 AV3 0.00 l
46 83 22 AV2 0.00 46 83 22 AV3 0.00 50 83 46 AV4 0.00 i
27 84 21 AV5 0.00 47 G4 34 AV4 0.00 l
49 84 27 AV3 0.00 49 84 30 AV4 0.00 49 84 28 AV5 0.00 I
42 89 22 AV4 0.00 48 89 33 AV3 0.00 I
49 90 40 AV2 0.00 i
39 91 24 AV4 0.00 48 92 38 AV2 0.00 48 92 25 AV4 0.00 h
48 92 21 AV6 0.00 i
48 93 40 AV3 0.00
{
49 94 21 AV2 0.00 49 94 24 AV5 0.00 36 110 28 AV3 0.00 36 110 4F AV4 0.00 36 110 27 AV6 0.00 l
32 112 30 AV6 0.00 33 112 30 AV4 0.00 Page 3 of 4
l SPECIAL REPORT TABLE 1 TUBE IMPERFECTIONS - STEAM GENERATOR 'D' INDICATION %
INCH ( + ) FROM ROW COLUMN WALL THINNING LOCATION LOCATION 33 112 40 AV5 0.00 32 113 22 AV2 0.00 32 113 22 AV6 0.00 r
Page 4 of 4