SBK-L-14137, 10 CFR 72.48 Report of Changes, Tests, and Experiments

10 CFR 72.48 Report of Changes, Tests, and Experiments

ML14230A098
Person / Time
Site:	Seabrook
Issue date:	08/07/2014
From:	Ossing M NextEra Energy Seabrook
To:	Document Control Desk, NRC/NMSS/SFST
References
SBK-L-14137
Download: ML14230A098 (3)

Text

NEXTera ENERGY

August 7, 2014 Docket No. 50-443 Docket No. 72-63 SBK-L-14137 ATTN: Document Control Desk Director, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Seabrook Station 10 CFR 72.48 Report of Changes, Tests, and Experiments 10 CFR 72.48(d)(2) requires that a report containing a brief description of changes, tests, and experiments, including a summary of the evaluation of each be submitted at intervals not to exceed 24 months. The enclosure provides a summary report of changes, tests, and experiments performed during the time period of August 1, 2012 through July 31, 2014.

Should you have any questions regarding this submittal, please contact me at (603) 773-7512.

Sincerely, NextEraich ne,,eabrook LLC Licensing Manager cc:

W. Dean, Regional Administrator, Region I J. Lamb, Project Manager, Project Directorate 1-2 P. Cataldo, Seabrook Senior Resident Inspector NextEra Energy Seabrook, LLC.

626 Lafayette Rd, Seabrook, NH 03874

Enclosure to SBK-L-14137 Summary Report of Facility Changes, Tests, and Experiments Completed in Accordance with the Requirements of 10 CFR 72.48 for the Time Period August 1, 2012 through July 31, 2014

10CFR72.48 Evaluation 13-001 Revision to 10 CFR 72.212 Evaluation Report Dry Fuel Storage Manual (DFSM) Chapter 2 Summary Description and

Purpose:

This activity revised the 10 CFR 72.212 Evaluation Report (Dry Fuel Storage Manual (DFSM) Chapter 2) to reflect the licensing basis for the 2013 loading campaign. The changes included adding Transnuclear (TN) FSAR Change Notices (FCNs) in Table 1.4.602 and the 2013 loading campaign was added as Section 1.4.6.c.

Reference and design changes listed in the report were administratively updated and typographical errors corrected.

Evaluation Summary: The 10 CFR 72.48 evaluation performed for this change concluded the activity was administrative in nature and did not affect the status of any SSC. Therefore, there was no increase to the probability or consequence of any accident or malfunction, nor is the possibility of a different accident or malfunction created. There is no impact to any design basis limit for a fission product barrier and no evaluation methodology is involved. The evaluation determined that the revision to the 10 CFR 72.212 report could be implemented without prior NRC approval.