SBK-L-10118, 10 CFR 72.48 Report of Changes, Tests and Experiments

10 CFR 72.48 Report of Changes, Tests and Experiments

ML102300372
Person / Time
Site:	Seabrook
Issue date:	08/10/2010
From:	O'Keefe M NextEra Energy Seabrook
To:	Document Control Desk, NRC/NMSS/SFPO
References
SBK-L-10118
Download: ML102300372 (3)

Text

PNEXTeraM ENERGY SEABROK August 10, 2010 Docket No. 50-443 Docket No. 72-63 SBK-L-10118 ATTN: Document Control Desk Director, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards 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, 2008 through July 31, 2010.Should you have any questions regarding this submittal, please contact me at (603) 773-7745.Sincerely, NextEra Energy Seabrook, LLC Michael O'Keefe Licensing Manager cc: Regional Administrator, Region I Project Manager, Project Directorate 1-2 Seabrook Senior Resident Inspector NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874 Enclosure to SBK-L-10118 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, 2008 through July 31, 2010 lOCFR72.48 Evaluation 08-001 Revision to 10 CFR 72.212 Evaluation Report Dry Fuel Storage Manual (DFSM) Chapter 2 Summary Description and Purpose: The evaluated activity involved administrative corrections to the 10 CFR 72.212 Evaluation Report (Dry Fuel Storage Manual (DFSM) Chapter 2). The changes included the renumbering of tables and correcting the radiological classification of the Dry Fuel Storage (DFS) facility from a Radiologically Controlled Area to a Restricted Area in accordance with the Radiation Protection Manual.Evaluation Summary: The 10 CFR 72.48 evaluation performed for this change concluded that the change was administrative in nature and did not affect the function of any structures, systems or components (SSC). Therefore, there was no increase to the probability or consequences of any accident or malfunction, nor was the possibility of a different accident or malfunction created. There was no impact to any design basis limit for a fission product barrier and no evaluation methodology was involved.

The evaluation determined that the corrections could be implemented without prior NRC approval.