BVY 12-056, Update to Deviation from BWRVIP-25 Inspection Requirements
| ML12255A002 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 09/06/2012 |
| From: | Wamser C Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BVY 12-056 | |
| Download: ML12255A002 (2) | |
Text
SEnteWgy Entergy Nuclear Operations, Inc.
Vermont Yankee 320 Governor Hunt Rd Vernon, VT 05354 Tel 802 257 7711 Christopher J. Wamser Site Vice President BVY 12-056 September 6, 2012 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
REFERENCES:
Update to Deviation from BWRVIP-25 Inspection Requirements Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28
- 1.
Letter, Entergy to USNRC, "Deviation from BWRVIP-25 Inspection Requirements," BVY 11-024, dated March 18, 2011
- 2.
Letter, Entergy to USNRC, "Core Plate Hold Down Bolt Inspection Plan and Analysis," BVY 11-021, dated March 18, 2011
- 3.
Letter, Entergy to USNRC, "Response to Request for Additional Information Regarding Core Plate Hold-down Bolt Inspection Plan and Analysis," BVY 12-008, dated February 1, 2012
Dear Sir or Madam:
In Reference 1, Vermont Yankee Nuclear Power Station (VY) provided notification to the NRC of a deviation from the BWR Vessel and Internals Project (BWRVIP), BWR Core Plate Inspection and Flaw Evaluation Guidelines (BWRVIP-25) inspection requirements for the core plate rim hold-down bolts. The VY technical justification for the deviation included an analysis that showed that postulated flaw growth over a 60-year lifetime would not significantly reduce bolt preload. VY has re-performed the technical justification for the deviation using the analysis submitted in Reference 2. The Reference 2 analysis did not use postulated flaw growth in determining the predicted loss of bolt preload, rather it used a stress analysis consistent with BWRVIP-25 Appendix A. This letter serves to notify the NRC that the VY technical justification for the deviation has been revised to use the Reference 2 analysis as a basis for the deviation.
This letter does not alter or revise the Reference 2 analysis nor does it alter or revise the hold-down bolt inspection plan submitted in Reference 3.
This letter is being transmitted for information only and VY is not requesting any action from the NRC staff.
There are no new regulatory commitments in this letter. Should you have any questions or require additional information concerning this submittal, please contact Mr. Robert Wanczyk at 802-451-3166.
Sincerely
[cJw/plc]
Acol
Pl VY 12-056 /Page 2of 2 cc:
Mr. William M. Dean Region 1 Administrator U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Mr. Richard V. Guzman, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 08C2A Washington, DC 20555 USNRC Resident Inspector Vermont Yankee Nuclear Power Station 320 Governor Hunt Road Vernon, VT 05354 Ms. Elizabeth Miller Commissioner VT Department of Public Service 112 State Street, Drawer 20 Montpelier, VT 05620-2601