SBK-L-12186, Second Annual Update to the NextEra Energy Seabrook License Renewal Application
| ML12268A171 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/18/2012 |
| From: | Walsh K NextEra Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SBK-L-12186 | |
| Download: ML12268A171 (7) | |
Text
NEXTeraM ENERGY.,ý'1/4 SEABROK September 18, 2012 SBK-L-12186 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 Second Annual Update to the NextEra Energy Seabrook License Renewal Application
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-1 1173, "Seabrook Station First Annual Update to the Seabrook Station License Renewal Application," August 25, 2011.
(Accession Number ML11241A142)
In Reference 1, NextEra Energy Seabrook, LLC (NextEra) submitted an application for a renewed facility operating license for Seabrook Station Unit I in accordance with the Code of Federal Regulations, Title 10, Parts 50, 51, and 54.
The License Renewal Rule, 10 CFR 54.21(b) requires that each year following submittal of a license renewal application (LRA), and at least 3 months before scheduled completion of the NRC review, an update to the license renewal application must be submitted that identifies any change to the current licensing basis (CLB) of the facility that materially affects the content of the LRA including the FSAR supplement.
In accordance with the License Renewal Rule, NextEra Energy Seabrook, LLC performed a review of CLB changes since the submittal of Reference 1, to determine whether any sections of the LRA were affected by these changes. The results of this first review were documented in NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
United States Nuclear Regulatory Commission SBK-L-12186 / Page 2 Reference 2 and submitted to the NRC in August of 2011.
NextEra Energy Seabrook, LLC has subsequently performed a second review of CLB changes since the submittal of Reference 2, to determine whether any sections of the LRA were affected by these changes. The results of the review are reported,in Enclosure 1. This update also includes a review of plant specific and industry operating experience for the same time period.
There are no new or revised regulatory commitments contained in this letter.
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 Manger, at (603) 773-7745.
Sincerely, NextEra Energy Seabrook, LLC.
Kevin T. Walsh Site Vice President
Enclosures:
- Second Annual Update to the Seabrook Station License Renewal Application cc:
W.M. Dean, NRC Region I Administrator J. G. Lamb, NRC Project Manager, Project Directorate 1-2 J. Grieves, NRC Resident Inspector A.D. Cunanan NRC Project Manager, License Renewal M. Wentzel, 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
United States Nuclear Regulatory Commission SBK-L-12186 / Page 3 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-12186 / Page 4 NEXTera ENERO'Y" i 1, Kevin T. 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 day of September, 2012 Kevin T. Walsh Site Vice President 4otary Public to SBK-L-12186 Second Annual Update to the Seabrook Station License Renewal Application
United States Nuclear Regulatory Commission Page 2 of 3 SBK-L-12186 / Enclosure 1
- 1. During the period covered by this update, a body to bonnet leak on a 6" Safety Injection system (SI) valve necessitated installation of a seal cap. This cap is designed to encapsulate the body to bonnet joint as well as the bonnet closure studs and nuts. This design, if left as a permanent installation, would preclude inspection of the bolting and a portion of the valve bolting as required by the applicable Aging Management Programs. In Seabrook Letter SBK-L-12123 (ML12178A405), dated June 19, 2012, NextEra changed the License Renewal Application Appendix A, Section A.2.1.9, Page A-9, and added a statement that "removal of the seal cap enclosures and restoration of the original configuration is planned to be completed no later than December 31, 2014".
Because the condition created by installation of this seal cap is planned to be removed by no later than December 31, 2014 (which is prior to entering the Period of Extended Operation), no further change to the License Renewal Application is necessary.
- 2. A normally closed valve was installed in the Fire Protection header supplying the Control Building and Diesel Generator Building hose reels. A bypass line with a flow-restricting orifice was installed around this valve to limit the flow from a rupture of downstream piping. As a result, the following changes to the LRA have been made:
a) In Section 2.3.3-15, on page 2.3-146, under the System Description for the Fire Protection System, a new paragraph is added after the 3rd paragraph as follows:
To limit break flow in the event of a Fire Protection piping rupture, a normally closed valve is installed in the header supplying the Control Building and Diesel Generator Building hose reels. A bypass line with a flow-restricting orifice is installed around this valve to limit the flow from a rupture of downstream piping, but still allow adequate flow to support use of downstream hose reels.
The valve is installed to allow additional flow to the downstream hose reels at the firefighters' discretion. The valve, bypass line, and orifice are installed in the Radiological Controlled Area Walkway.
b) In Table 2.3.3-15, on page 2.3-151, a new row is added after the 6th row as follows:
United States Nuclear Regulatory Commission Page 3 of 3 SBK-L-12186 / Enclosure 1 c) In Table 3.3.2-15, on page 3.3-306, new 1st and 2nd rows are added as follows:
Pressure PressureAir-Indoor Orifice Boundary Stainless Andoor VII. J-15 3.3.1-94 A
OfieStee Uncontrolled None None (AP-1 7) 3319 Throttle (External)
Pressure Fire Water Orifice Boundary Stainless Raw Water Loss of System VII.G-19 3.3.1-69 A
Throttle Steel (Internal)
Material Program (A-55)