RC-03-0191, Withdrawal of Request for Relief (0-C-02-3202) (RR-II-09, RR-II-10, RR-II-11, and RR-II-12) Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI
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Letter Sequence Withdrawal | |
|---|---|
TAC:MB6647, (Withdrawn, Closed) | |
MONTHYEARRC-03-0191, Withdrawal of Request for Relief (0-C-02-3202) (RR-II-09, RR-II-10, RR-II-11, and RR-II-12) Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI2003-09-11011 September 2003
[Table View]Withdrawal of Request for Relief (0-C-02-3202) (RR-II-09, RR-II-10, RR-II-11, and RR-II-12) Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI Project stage: Withdrawal RC-05-0094, Response to Request for Additional Information Regarding Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI Relief Request RR-11-9 and RR-11-10 (C-02-3202)2005-06-22022 June 2005 Response to Request for Additional Information Regarding Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI Relief Request RR-11-9 and RR-11-10 (C-02-3202) Project stage: Response to RAI 2003-09-11 |
| ML032590722 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/11/2003 |
| From: | Byrne S South Carolina Electric & Gas Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RC-03-0191, TAC MB6647 | |
| Download: ML032590722 (2) | |
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Category:Code Relief or Alternative
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Text
Stephen A. Byrne Senior Vice President, Nuclear Operations 803.345.4622 September 11, 2003 A SCANA COMPANY RC-03-01 91 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir / Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 WITHDRAWAL OF REQUEST FOR RELIEF (0-C-02-3202)
(RR-11-09, RR-11-10, RR-11-1 1, and RR-11-12)
REQUEST TO USE ALTERNATIVES TO ASME BOILER AND PRESSURE VESSEL CODE, SECTION Xl - TAC NO. MB6647
Reference:
Stephen A. Byrne (SCE&G) letter RC-02-0191 to Document Control Desk (NRC), dated October 30, 2002 In the above referenced letter, South Carolina Electric & Gas Company (SCE&G),
submitted a request for relief from performing examination to the criteria of the American Society of Mechanical Engineers (ASME), Section Xi, regarding Steam Generator Nozzle Inner Radius, Class 1 and 2 Piping, Class 2 Vessel, Class 1 Vessel, and Class 1 Bolting.
A public meeting between the V. C. Summer Nuclear Station (VCSNS) NRR Project Manager, the NRC technical reviewer, and SCE&G was held on August 8, 2003, at NRR offices. The technical reviewer discussed several issues with four of the requests submitted by SCE&G (Reference 1).
Based on this meeting, SCE&G wishes to withdraw the following requests:
RR-11-09 (Attachment II to Reference 1),
RR-11-10 (Attachment Ill to Reference 1),
RR-11-1 1 (Attachment IV to Reference 1), and RR-11-12 (Attachment V to Reference 1).
AD1 SCEUG I Virgil CSummer Nudear Staton . P.0.Box 88. Jenk- v le. South arolina 29065 eT(803) 345.5209 .wwwscon.con
Document Control Desk O-C-02-3202 RC-03-01 91 Page 2 of 2 Based on a conversation with the NRC, SCE&G will resubmit RR-II-9, 10, and 11 using VCSNS historical examination data reports for these welds as the basis for relief. If RF-14 examination results exceed the reference numbers established by the VCSNS historical data, SCE&G will submit new relief requests for the affected welds based on the results.
SCE&G will resubmit RR-11-12 based onASME Code Case N 307-3.
These requests, with the recommended formats, will be resubmitted as soon -as possible in order for the NRC to perform an expeditious review and approval, as they are needed for implementation at our approaching refueling outage.
Should you have questions, please call Mr. Ron Clary at (803) 345-4757.
Very truly yours A.Byme d /.,j JT/SAB/dr c: N. O. Lorick N. S. Cams T. G. Eppink R. J. White L. A. Reyes K. R. Cotton K. M. Sutton NRC Resident Inspector NSRC RTS (0-C-02-3202)
File (810.19-2)
DMS (RC-03-0191)