RS-08-072, Withdrawal of Third 10-Year Inservice Inspection Interval Relief Request I3R-01
| ML081500828 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/29/2008 |
| From: | Simpson P Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| I3R-01, RS-08-072 | |
| Download: ML081500828 (2) | |
Text
Exelon Nuclear www.exeloncorp.com 4300 Winfield Road Warrenville, I L 60555 RS-08-072 10 CFR 50.55a May 29, 2008 U. S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Exelaln
Subject:
Withdrawal of Third 10-Year Inservice Inspection Interval Relief Request 13R-01 References :
1.
Letter from P. R. Simpson (Exelon Generation Company, LLC) to U. S.
Nuclear Regulatory Commission, "Third 10-Year Inservice Inspection Interval, Relief Request 13R-01, 'Request for Relief for Alternate Risk Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds,"' dated March 31, 2008
- 2.
Letter from M. J. David (U. S. Nuclear Regulatory Commission) to C. G.
Pardee (Exelon Generation Company, LLC), "Braidwood Station, Units 1 and 2 - Request for Supplemental Information Regarding Relief Request 13R-01 (TAC Nos. MD8456 and MD8457)," dated May 22, 2008 In Reference 1, Exelon Generation Company, LLC (EGC) requested relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, 2001 Edition through the 2003 Addenda, for Braidwood Station, Units 1 and 2. Specifically, Relief Request 13R-01 requested NRC approval to implement alternative risk-informed selection and examination criteria for certain pressure retaining piping welds.
In Reference 2, the NRC requested information regarding the quality of the Braidwood Station probabilistic risk assessment (PRA) model used to support the proposed relief request be provided by May 30, 2008. The information was requested because the NRC will use Revision 1 of NRC Regulatory Guide 1.200, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities," to assess the technical adequacy of the Braidwood Station PRA model.
Nuclear
U. S. Nuclear Regulatory Commission May 29, 2008 Page 2 EGC has performed a gap analysis of the Braidwood Station PRA model against a previous version of NRC Regulatory Guide 1.200. However, additional efforts are required to extend this analysis to Revision 1 of the regulatory guide and will not be completed by May 30, 2008. As a result, EGC is withdrawing the Reference 1 relief request.
This letter contains no regulatory commitments.
If you have any questions concerning this letter, please contact Mr. David Chrzanowski at (630) 657-2816.
Patrick R. Simpson Manager - Licensing