ML022670220
| ML022670220 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/16/2002 |
| From: | Byrne S South Carolina Electric & Gas Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RC-02-0161 | |
| Download: ML022670220 (5) | |
Text
Stephen A. Byrne 7
Senior Vice President, Nuclear Operations 803 345.4622 September 16, 2002 RC-02-0161 A SCANA COMPANY Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Ladies and Gentlemen:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 REQUEST FOR REVISION TO ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI RELIEF REQUEST (NRR 00-0058)
RR-I-07
Reference:
- 1. EPRI TR-112657, "Revised Risk-Informed Inservice Inspection Evaluation Procedure"
- 2. USNRC letter to Electric Power Research Institute (EPRI), dated October 28, 1999, regarding "Safety Evaluation Procedure (EPRI TR 112657, Revision B, July 1999)
South Carolina Electric and Gas Company (SCE&G) requests relief to use the proposed Risk-Informed Inservice Inspection Program (RI-ISI) [Attachment I] as an alternative to the current ASME Section XI inspection requirements for Class 1, Examination Category B-F and B-J, and Class 2, Examination Category C-F-1 and C-F-2 welds pursuant to 10 CFR 50.55a(a)(3)(i). The RI-ISI Program has been developed in accordance with the EPRI methodology contained in EPRI TR-1 12657, Revision B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure" (Reference 1). EPRI TR-1126557 was approved by the NRC Safety Evaluation Report, dated October 28, 1999 (Reference 2).
The attached VCSNS specific RI-ISI evaluation (Attachment II) supports the conclusion that the proposed alternative provides an acceptable level of quality and safety as required b.;
SCE&G plans to implement the initial VCSNS RI-ISI program during the inspection period in effect at the time of the program approval. The VCSNS Inservice Examination program will continue to evaluate industry events and experiences relative to the station Risk-Informed Inspection program. Relief request approval is requested by February 7, 2003, in support of Refueling Outage 14 (RF14) currently scheduled for the Spring of 2003.
SCE&G I Virgil C. Summer Nuclear Station ° P. 0. Box 88 ° Jenkinsville, South Carolina 29065.T (803) 345 5209
- www.scano.com
Document Control Desk NRR 00-058 RC-02-0161 Page 2 of 2 The relief request is included as an attachment to this letter.
Should you have any questions concerning the application or approval of this relief request, please contact Mr. Mel Browne at (803) 345-4141.
Very truly yours, Stephen A. Byrne JT/SAB/dr Attachment(s): Attachment I, except where noted. Attachment II available upon request.
c:
N. 0. Lorick N. S. Carns T. G. Eppink (w/o Attachments)
R. J. White L. A. Reyes K. R. Cotton NRC Resident Inspector K. M. Sutton NSRC R. Caban RTS (NRR 00-0058)
File (810.19-2)
DMS (RC-02-0161)
Document Control Desk Attachment I NRR 00-0058 RC-02-0161 Page 1 of 2 South Carolina Electric & Gas Co. (SCE&G)
Virgil C. Summer Nuclear Station (VCSNS)
Relief Request RR-11-07
Subject:
Implementation of Risk-Informed Inservice Inspection program.
Components Identification:
All pressure retaining components under the ASME Categories B-F, B-J, C-F-1 and C-F-2.
Current Code Requirement:
ASME Code, Section Xl, Table IWX-2500-1 for Examination Categories B-F, B-J, C F-1 and C-F-2 require specific percentages of the weld population to be inspected each inspection Interval.
RELIEF REQUEST:
Relief is requested from the IWB-Table-2500-1 and IWC-Table-2500-1 percentages of piping weld populations scheduled for examination.
Alternative Test:
Apply the Risk-Informed Inservice Inspection weld selection criteria as detailed in the EPRI TR-112657 V. C. Summer Nuclear Station (VCSNS) specific evaluation which is consistent with ASME Code Case N-578 during the second Interval inspection program.
Basis for Relief:
VCSNS is presently required to schedule piping weld inspections in accordance with the 1989 Edition of ASME Section XI. The current selection of welds for inspection is based on the inherent design stress intensity and usage factor. The alternative EPRI Topical Report-Number 112657 and Code Case N-578 require-extensive engineering evaluation of all piping segments subject to the ASME Section XI Inservice Examination Program. This engineering evaluation bases the selection and scheduling of piping welds on probable failure potential.
Document Control Desk Attachment I NRR 00-0058 RC-02-0161 Page 2 of 2 In accordance with the guidelines of the Code Case and the Technical Report, the piping systems subject to the Inservice Examination Program at VCSNS have been evaluated, categorized for failure potential and ranked relative to risk of failure. The "Risk-Informed Inservice Inspection Program Plan, V. C. Summer Nuclear Station, Revision 0" document (Attachment II) details the engineering evaluation and the specific piping segments selected for inspection selection. Therefore, the proposed alternative weld selection process will provide an acceptable level of quality without an increased level of risk.
-aI Document Control Desk Attachment II NRR 00-0058 RC-02-0161 Page 1 of 1 Risk-Informed Inservice Inspection Plan V. C. Summer Nuclear Station Revision 0