ML20207T704
| ML20207T704 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/18/1987 |
| From: | Rice P GEORGIA POWER CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-87, REF-PT21-87-075-000 GN-1347, PT21-87-075-000, PT21-87-75, NUDOCS 8703240260 | |
| Download: ML20207T704 (2) | |
Text
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George F0wer Company
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Fbst Offica Box 282 Waynesboro, Georg;a 30830 Telephons 404 554-9961. Extension '1413 404 724-8114. Extension D413 L
"7 f[B M ^ 7 d 9 Georgia Power P. D. Rice Vice President Vogtle Project try southem eectnc system February 18, 1987 United States Nuclear Regulatory Commission Region II, Suite 2900 File:
X78G03-M63 101 Marietta Street, Northwest Log:
GN-1347 Atlanta, Georgia 30323
Reference:
Vogtle Electric Generating Plant-Units 1 & 2; 50-424,50-425; Nuclear Service Cooling Water Supply and Return Piping; Letter GN-418, dated September 13, 1984 Attention:
Mr. J. Nelson Grace Georgia Power Company wishes to clarify corrective action information submitted in our previous correspondence on this subject (GN-418),
which identified a reportable condition pursuant to the requirements of 10CFR50.55(e) and 10CFR21.
The condition was caused by the erroneous assumption in the initial piping system stress calculation that the cooling tower and valve house were on a common base mat.
Thus, no differential motion was considered.
The corrective action for the reported condition is described in Part A of the corrective action section of the evaluation summary attached to GN-418.
The NSCW piping stress analyses for both Units 1 & 2 were updated to consider differential motion between the valve house and cooling tower.
This action was completed at the time GN-418 was submitted.
Part B of the corrective action section created some confusion during the USNRC inspection that closed CDR 84-63.
This section describes the subsequent use of the corrected stress analyses in the piping support loading verification program and, as GN-418 indicates, this work is continuing.
To date, implementation of the verification program for Unit 1 is complete and Unit 2 will be completed prior to fuel load.
This response contains no proprietary information may be placed in the USNRC Public Document Room.
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P. D. Rice
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February 18, 1987 File: X7BG03-M63 Log:
GN-1347 Page two CWH/PDR/wkl xc:
U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555 H. G. Baker D. R. Altman L. T. Gucwa J. P. O'Reilly J. A. Bailey C. W. Hayes G. F. Head O. Batum G. A. McCarley R. E. Conway G. Bockhold R. W. McManus R. H. Pinson C. E. Belflower Sr. Resident (NRC)
B. M. Guthrie J. F. D'Amico C. C. Garrett (OPC)
R. A. Thomas W. D. Drinkard J. E. Joiner (TSLA)
E. D. Groover D. Feig (GANE)
NORMS