ML20199L074
| ML20199L074 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/29/1998 |
| From: | Mccoy C SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LCV-1016-G, NUDOCS 9802090113 | |
| Download: ML20199L074 (2) | |
Text
. __ _______- _____ - - ___ - __ _ _
w C.lk <cCoy Southern Nuclest Vice President Operating Company,Inc.
Vogtle Project -
40 invorr:ss Cent:r Parkway 4
PO tbx1295 Derningham, Alahana 35201 Tel2059323122 Iax 205932.0403 SOUTHERN COMPANY Energy to Serve Yourtrorld" January 8, 1998 LCV-1016-G Docket Nos.: 50-424, 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk l
Washington, D. C. 20555 Ladies and Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT l
CLARIFICATION TO INSERVICE INSPECTION PROGRAM REOUEST FOR RELIEF RR-20 By letter LCV-1016 dated May 29,1997, Southern Nuclear Operating Company (SNC) submitted the Second Ten Year Inservice Inspection Program for the Georgia Power Company-owned Vogtle Electric Generating Plant (VEGP), Units 1 and 2. Contained therein was Request for Relief RR 20 which requested NRC approval for the use of ASME Section XI Code Case N 509," Alternative Rules for the Selection and Examination of Class 1,2, and 3 Integrally Welded Attachments". Use of the subject Code Case requires that ten percent (10%) of the integrally welded Stachments for vessels, piping, pumps, and valves be examined.
Recent communication with NRC staff suggests that our Request for Relief RR-20 does I g not explicitly state that 10% of the integrally welded attachments for vessels, piping, pumps, and valves will be examined if ASME Section XI Code Case N-509 is used. As a result, we wish to clarify our proposed use of the subject Code Case. SNC will examine a
. minimum of 10% of the ASME Section XI integrally welded attachments in each piping, pump, and valve examination item number listed in ASME Section XI Code Case N-509, Table 25001. These examinations will be distributed among the non-exempt integrally welded attachments in each piping system contained in VEGP's Class 1,2, and 3 systems and components. In the case of the examination item numbers relating to pressure vessels, j
Note 4 of Table 2500-1 will be used in the selection ofintegrally welded attachments to be l
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U. S. Nuclear Regulatory Commission
- LCV f016-G Page Two 3
h canine.d. This will result in over 10% of the tntal pressure vessel integrally welded atta:;hments being selected for examination.
With our having provided clarification on the proposed us of ASME Section XI Code Case N-509, we respectfully request that you expediticus'.y complete your review of 73 Renuest for Relief RR-20 so tilat it may used during VEGP 2 Maintenance / Refueling Outage 2R6 which is currently scheduled to begia March S.199R.
Should there be any questions in this regard, please contact th:s office.
Sincerely, 0411' C. K. McC[
CKM/JAE/jae xc: INEEL Research Center Mr. M. T. Anderson
.SRuLhun Nuclear Operating Company Mr. J. B. Beasley, Jr.
- Mr. W. L. Burmeister Mr. M. Shettani NORMS U. S. Nuclear Regulatory Commission Mr. D. H. Jaffe, Senior Project Manager, NRR r
Mr. L. A. Reyes, Regional Administrator Senior Resident Inspector, Vogtle c
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