ML16158A018
| ML16158A018 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  (NPF-086) |
| Issue date: | 06/10/2016 |
| From: | Justin Poole Plant Licensing Branch 1 |
| To: | Mccartney E NextEra Energy Seabrook |
| Poole J, NRR/DORL/LPLI-2, 415-2048 | |
| References | |
| CAC MF7565 | |
| Download: ML16158A018 (3) | |
Text
Mr. Eric McCartney Site Vice President Seabrook Station NextEra Energy 626 Lafayette Rd.
Seabrook, NH 0387 4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 10, 2016
SUBJECT:
SEABROOK STATION, UNIT NO. 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REQUEST TO EXTEND CONTAINMENT LEAKAGE TEST FREQUENCY (CAC NO. MF7565)
Dear Mr. McCartney:
By letter dated March 31, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16095A278), as supplemented by letter dated May 31, 2016 (ADAMS Accession No. ML16159A194), NextEra Energy Seabrook, LLC submitted a license amendment for the Seabrook Station, Unit No. 1. The proposed amendment would 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 NEI 94-01, Revision 3-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J" (ADAMS Accession No. ML12221A202).
The proposed change will allow extension of the Type A test interval up to one test in 15 years and extension of the Type C test interval up to 75 months, based on acceptable performance history as defined in NEI 94-01, Revision 3-A. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review.
The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application, including the supplemental information provided in the May 31, 2016, letter, and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment.
Given the lesser scope and depth of the acceptance review as compared to the detailed
technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
If you have any questions, please contact me at (301) 415-2048 or Justin.Poole@nrc.gov.
Docket No. 50-443 cc: Distribution via Listserv Sincerely, Justin C. Poole, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML16158A018 OFFICE NRR/DORL/LPL 1-2/PM NRR/DORL/LPL 1-2/LA NRR/DORL/LPL 1-2/BC NRR/DORL/LPL 1-2/PM NAME JPoole LRonewicz DBroaddus JPoole DATE 6/9/2016 6/7/2016 6/10/2016 6/10/2016