SBK-L-17163, 7 - Revision to License Renewal Application 10 CFR 50 Appendix J Program
| ML17278A955 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 10/06/2017 |
| From: | Mccartney E NextEra Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CAC MF7565, SBK-L-17163 | |
| Download: ML17278A955 (5) | |
Text
October 06, 2017 10 CFR 54 Docket No. 50-443 SBK-L-17163 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station NEXTera ENERGY.
SEABROOK Supplement 57 - Revision to License Renewal Application 10 CFR 50 Appendix J Program
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-16029, "License Amendment Request 16-01 Request to Extend Containment Leakage Test Frequency," March 31, 2016 (Accession Number ML16095A278).
- 3. NRC, "Seabrook Station, Unit No. 1 - Issuance of Amendment Re: Extension of Containment Leakage Rate Test Frequency (CAC No. MF7565)," March 15, 2017 (Accession Number ML17046A443).
In Reference 1, NextEra Energy Seabrook, LLC (NextEra Energy Seabrook) 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 Energy Seabrook requested a license amendment to revise Technical Specification 6.15, Containment Leakage Rate Testing Program, to require a program that is in accordance with Nuclear Energy Institute (NEI) topical report (TR) 94-01, Revision 3-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J" and the conditions and limitations specified in NEI TR 94-01, Revision 2-A.
NextEra Energy Seabrook, LLC P.O. Box 300, Lafayette Road, Seabrook, NH 03874
U.S. Nuclear Regulatory Commission SBK-L-17163 /Page2 In Reference 3, the NRC issued Amendment No. '153 to NextEra Energy Seabrook. The amendment revised Seabrook's Technical Specification 6.1 5, "Containment Leakage Rate Testing Program," to be in accordance with NEI TR 94-01, 3-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," and the conditions and limitations specified within NEI TR 94-01, Revision 2-A.
Based on issuance of Amendment No. 153, NextEra Energy Seabrook has revised License Renewal Application (LRA), Appendix B - Aging Management Programs, B.2.1.30 - 10 CFR Part 50 Appendix J, as shown in the Enclosure.
To facilitate understanding, the changes are explained, and where appropriate, portions of the LRA are repeated with the change highlighted by strikethroughs for deleted text and balded italics for inserted text.
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.
Edward J. Carley, Engineering Supervisor - License Renewal, at (603) 773-7957.
If you have any questions regarding this correspondence, please contact Mr. Kenneth Browne, Licensing Manager, at (603) 773-7932.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on October ?
, 2017.
~--
Sincerely, NextEra Energy Seabrook, LLC
U.S. Nuclear Regulatory Commission SBK-L-17163 I Page 3
Enclosure:
Supplement 57 - Revision to License Renewal Application Appendix B -
Aging Management Programs, B.2.1.30 - 10 CFR Part 50 Appendix J.
cc:
D. H. Dorman J.C. Poole P. C. Cataldo L. M. James Mr. Perry Plummer NRC Region I Administrator NRC Project Manager NRC Senior Resident Inspector NRC Project Manager, License Renewal 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 perry.plummer@dos.nh.gov Mr. John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 John. Giarrusso@massmail.state.ma. us
Enclosure to SBK-L-17163 Supplement 57 - Revision to License Renewal Application Appendix B - Aging Management Programs, B.2.1.30 - 10 CFR Part 50 Appendix J
U.S. Nuclear Regulatory Commission SBK-L-17163 I Enclosure I Page 2 Amendment No. 153 (Reference 3) revised NextEra Energy Seabrook's Technical Specification 6.15, "Containment Leakage Rate Testing Program, to be in accordance with Nuclear Energy Institute (NEI) topical report (TR) NEI 94-01, 3-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J,
and the conditions and limitations specified within NEI TR 94-01, Revision 2-A.
Seabrook's LRA, Appendix B - Aging Management Programs, B.2.1.30 - 10 CFR Part 50 Appendix J, Program Description, third paragraph, is revised below.
10 CFR Part 50 Appendix J, Option B applies guidance provided in NRG RG 1.163, "Performance Based Containment Leak Test Program", for performance based leak testing.
NRG RG 1.163 accepts methods provided in is in accordance with the guidance in Nuclear Energy Institute (NEIJ Topical Report (TR) 94-01, Revision 3-A, "Industry Guideline for Implementing Petformance-Based Option of 10 CFR Part 50, Appendix J", and the conditions and limitations specified in NE/ TR 94-01, Revision 2-A. for implementing performance based testing 1Nith restrictions. NRG RG 1.163 also accepts the methods and techniques for performing Type A, B and C tests contained in ANSI/ANS 56.8 1994, "Containment System Leakage Testing Requirements".
The Seabrook Station Leakage Test Reference is based on the guidance provided in NEI TR 94-01, Revision 3-A, and ANSI I ANS-56.8--1-994 2002. with the restrictions identified in RG 1.163.