ML20092K365
| ML20092K365 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/04/1984 |
| From: | Foster D GEORGIA POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| GN-368, NUDOCS 8406280295 | |
| Download: ML20092K365 (3) | |
Text
4 Georgia Power Corrcan j
P1 Rcuta 2. Bon 299A g
o Wayniscoro. Georgia 30830 PRP 0FFICIAL COPY
,e tiephona 404 554 9961. Est 3360 4C4 724 8114. Eat 3360 g
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i,a Georgia Power D. O. Fost.,
V'ce Pres dent and Protect General Manager 1' N " C" C 5
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Vogne P c:act June 4, 1984 United States Nuclear Regulatory Comission File:
X78G03-M57 Office of Inspection and Enforcement Log:
GN-368 Region II - Suite 3100 101 Marietta Street Atlanta, Georgia 30302
Reference:
Vogtle Electric Generating Plant-ilnit 1, 50-424; Reactor Coolant Crossover Leg Elbow, GPC letter to NRC, GN-343, dated 4/18/84.
Attention: Mr. James P. O'Reilly Gentlemen:
In the above referenced letter, Georgia Power Company indicated that the NRC could expect to receive a final report on this subject by June 6, 1984.
Georgia Power Company has received various reports from Westinghouse Electric and its architect / engineers and has concluded that the indication discovered on the reactor coolant crossover leg elbow does not constitute a reportable condition.
This letter contains no proprietary information and may be placed in the NRC Public Document Room upon receipt.
.p Yo r -truly,
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D. O. Foste'r M 0F/tdm xc:
U. S. Nuclear Regulatory Comission Document Control Desk Washington, D. C.
20555 R. J. Kelly D. E. Dutton J. A. Bailey L. T. Gucwa R. E. Conway W. F. Sanders
- 0. Batum M. Malcom G. F. Head R. H. Pinson G. Bockhold H. H. Gregory, III C. W. Hayes P. D. Rice B. M. Guthrie J. T. Beckham, Jr.
D. N. MacLemore R. A. Thomas E. D. Groover J. L. Vota l
8406280295 840604
.-OFFICIAL COPf PDR ADOCK 05000424
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i EVALBATION~FOR A SUBSTANTIAL SAFETY HAZARD EVALUATION FOR A SIGNIFICANT DEFICIENCY Reactor Coolant Crossover Leg Elbow i
Initial Report:
On March 20, 1984, Mr. C. W. Hayes of Georgia Power Company reported to Mr. John Rogge of the USNRC a potential deficiency concerning an indication detected on the reactor coolant system crossover leg elbow.
Georgia Power Company, in an interim report on April 18, 1984, stated that the NRC could expect a final report on this subject by June 6, 1984.
Background Information:
On October 9,1983, Pullman Power Products initiated 'n'onconformance report MD-6028 for an indication detected on the reactor coolant system elbow for i
steam generator number 3, weld 005-W-02. This indication was observed to be linear in nature,1-3/4" long, and orientated in an axial oirection approximately 5/8" away from the toe of the weld.
Pullman Power Products proceeded to l'ightly buff the questionable area.
The light buffing did not clear the indication, but caused it to open up.
i' Upon receipt of the Pullman Power Products nonconformance report MD-6028, Westinghouse site personnel conducted a visual examination of the subject area.
The Westinghouse site welding engineer noted the buffing in the area of interest and, using SX and 10X magnification, he observed traces of arcing and molten metal.
This indicated that the surface may have been subjected to an arc strike and weld splatter.
Westinghouse personnel also reviewed the Quality Data Package for the elbow to determine if any problems had been encountered in this area by the 4
fitting supplier. ESCO Corporation. These records confirmed that the machined weld preparation end had undergone two radiographic examinations (i.e. as-c:st and machined) in accordance with Paragraph NB-2573 of ASME Code Section III 1971 criteria of ASTM E186-67, severity level 2.
A further check of the liquid penetrant examination records established i
that all examinationf of the elbow during field fit-up prior to welding showed smoothly machined weld end surfaces.
Engineering Evaluation:
After buffing, the resultant cavity measured 2-1/4" long x l-1/4" wide x 0.150 inches deep.
The as-built measured thickness in the areas was recorded as 3.10" while the minimum required thickness is 2.48".
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Therefore, the blended cavity with a depth of 0.150" would not result in a violation of the minimum wall thickness requirement.
Even though I
the cavity could have been left "as-is", it was weld repaired to restore the surface to the original dimensions.
S s..
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Reactor Coolant 3roisayer Leg Elbow Pag 7 2 4
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Conclusion:==
Since the cavity could have been left "as-is" there cannot be an adverse affect upon the future safe operations of the plant.
Therefore it can be concluded that a reportable condition does not exist.
Quality Assurance Program Review:
A review has also been made of the various quality assurance programs and it has been determined that there has not been a quality assurance program breakdown.
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