ML20117F166
| ML20117F166 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 05/13/1996 |
| From: | Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9605170213 | |
| Download: ML20117F166 (2) | |
Text
',
South Carolina Electric & Gas Comptny Gary J.Trylor P.O. Box 88 Vice President Jenkinsville, SC 29065 Nuclear Operations
-=
(803) 345-4344 SCE&G A SCIUmQxnpany May 13, 1996 j
Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 4
Attention: Mr. A.R. Johnson Gentlemen:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO.50/395 OPERATING LICENSE NO.NPF-12 SPECIAL REPORT (SPR 960004)
This special report is being submitted pursuant to the requirements of the Virgil C.
l Summer Nuclear Station Technical Specifications, Section 4.4.5.5.a and Section 4.4.5.5.b.
Section 4.4.5.5.a requires that a Special Report be submitted, within 15 days following the completion ofinservice inspection of Steam Generator tubes, indicating the number i
of tubes plugged or repaired in each generator. The inspection activity was completed on April 29,1996. Summarized in the table below is the number of plugs installed in i
each generator as a result of the inspections performed during the ninth refueling outage.
Generator A
B C
Total Plugged 0
0 0
0 Currently there are two plugs in Steam Generator "C" and one plug in Steam Generator "B" as a result ofinspections performed prior to installing the replacement Steam Generators.
Section 4.4.5.5.b requires that within 12 months following the completion of the inservice inspection of the generators, the complete results be submitted to the Commission as a Special Report. This information is provided below:
1.
The number and extent of the tubes inspected.
Steam Generator "A" - 1893 tubes (approximately 22%)
Steam Generator "B" - 1039 tubes (approximately 16%)
Together these comprise approximately 13% of the total tube population of the three Steam Generators. These tubes were inspected from tube end to tube end (full length) using the bobbin coil eddy current technique.
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Document Control Desk SPR 960004 - RFL 300 RC-96-0132 Page 2 of 2 2.
Location and percent of wall thickness penetration for each indication of animperfection.
A total of two tubes were identified with imperfectiono. Both of the indications in the reported tubes were present in the baseline examination performed in August 1994, prior to installation of the steam generators.
These tubes are:
> Steam Generator "A" - Row 113, Column 72, sixth support plate plus 10.09 inches on the outlet side. The imperfection depth was not quantifiable.
> Steam Generator "B"- Row 52, Column 11, ninth support plate plus 1.09 inches on the outlet side. The imperfection depth is less than 20% of nominal wall thickness.
3.
Identification of tubes plugged.
No tubes were plugged during this inspection interval.
VCSNS response to Generic Letter 95-03, dated February 1,1996, stated that examination of100 intersections will be done using 3-coil"plus point" MRPC techniques during the RF-9 inspection of our Steam Generators. The tubes selected for this additionalinspection scope would be the ones exhibiting bobbin coilindications that may require further characterization. Since there were no new indications detected utilizing the bobbin coil technique, the scope was not expanded to include MRPC examinations.
Should you have questions on the above, please call Mr. Philip Rose at (803) 345-4052.
Very truly yours, Q
Gar or-PAR /GJT/dr c:
J. L. Skolds R. E. Kelso W. F. Conway J. B. Knotts Jr.
R. R. Mahan INPO Records Center R. J. White RTS(ONO 960235, RFL 300)
S. D. Ebneter File (818.05)
NRC ResidentInspector DMS (RC-96-0132)
S. F. Fipps NUCLEAR EXCELLENCE - A SUMMER TRADITION!
J