SBK-L-12247, Clarification for Response to Follow Up RAI B.2.1.31-1 Item (b)(2) Provided in SBK-L-12217, November 2, 2012
| ML12333A237 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 11/20/2012 |
| From: | Walsh K NextEra Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SBK-L-12247 | |
| Download: ML12333A237 (4) | |
Text
NEXTeram ENERG Y f
SEABROOK November 20, 2012 SBK-L-12247 Docket No. 50-443 U.S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 Seabrook Station Clarification for Response to Follow up RAI B.2.1.31-1 Item (b)(2) provided in SBK-L-12217, November 2, 2012
References:
- 1. NextEra Energy Seabrook, LLC letter SBK-L-10077, "Seabrook Station Application for Renewed Operating License," May 25, 2010. (Accession Number ML101590099).
- 2. NextEra Energy Seabrook, LLC letter SBK-L-12217, "Seabrook Station Response to Request for Additional Information, NextEra Energy Seabrook License Renewal Application - Request for Additional Information", November 2, 2012.
In Reference 1, NextEra Energy Seabrook, LLC (NextEra) submitted an application for a renewed facility operating license for Seabrook Station Unit 1 in accordance with the Code of Federal Regulations, Title 10, Parts 50, 51, and 54.
In Reference 2, NextEra provided a response to an ASR related Request for Additional Information.
This Supplement is submitted to clarify the response to Follow up RAI B.2.1.31-1 item (b)(2) provided in NextEra letter SBK-L-12217 dated November 2, 2012. To facilitate understanding, the clarification to the original response is highlighted by bolded italics for inserted text.
There are no new or revised regulatory commitments contained in this letter.
NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
United States Nuclear Regulatory Commission SBK-L-12247/Page 2 If there are any questions or additional information is needed, please contact Mr. Richard R.
Cliche, License Renewal Project Manager, at (603) 773-7003.
If you have any questions regarding this correspondence, please contact Mr. Michael O'Keefe, Licensing Manager, at (603) 773-7745.
Sincerely, NextEra En Seabrook, LLC.
Kevin T. Walsh Site Vice President cc:
W.M. Dean, NRC Region I Administrator J. G. Lamb, NRC Project Manager, Project Directorate 1-2 S. Rich, NRC Senior Resident Inspector P.D. Milano, NRC Project Manager, License Renewal L.M. James, NRC Project Manager, License Renewal Mr. Christopher M. Pope Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399
United States Nuclear Regulatory Commission SBK-L-12247/ Page 3 NExTera
- ENERGY, SEABROOK I, Kevin Walsh, Site Vice President of NextEra Energy Seabrook, LLC hereby affirm that the information and statements contained within are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.
Sworn and Subscribed Before me this o,2 "i-day of November, 2012 Kevin T. Walsh IA.,
/2 Site Vice President
United States Nuclear Regulatory Commission SBK-L-12247/Page 4 Clarification for Response to (b)(2) of Follow up RAI B.2.1.31-1 provided in SBK-L-12217, November 2, 2012:
Request for Follow up RAI B.2.1.31-1 b) Clarify whether the acceptance criteria is the one stated in the ASR Monitoring Program, or the one described in the March 30, 2012, response which indicates that the acceptance criteria will correlate the degradation of mechanical properties to cracking, based on testing at the University of Texas.
NextEra Energy Response (b)(2) On page 6 of 18 of Enclosure 1 of SBK-L-12217, the following new paragraph is added after the first paragraph as follows To manage the aging effects of cracking due to expansion and reaction with aggregates in concrete structures, the existing Structures Monitoring Program, B.2.1.31, has been augmented by a plant specific Alkali-Silica Reaction (ASR)
Monitoring Program, B.2.1.31A. The ASR Monitoring Program will be structured according to the guidelines in ACI 349.3R, "Structural Condition Assessment of Buildings."
NextEra has also initiated actions to perform testing on full-scale replicas of station structural configurations. Information from these test results will be utilized in any required structural evaluations. In the event these test results indicate a need to amend either the monitoring program acceptance criteria or the frequency of monitoring, NextEra will take such action under the Operating Experience element of the ASR Monitoring Program.
There are no preventive actions specified in the Seabrook Station Structures Monitoring Program, which includes implementation of NUREG-1801 XI.S5, XI.S6, and XI.S7. These are monitoring programs only. Similarly, the ASR Monitoring Program does not rely on preventive actions.