SBK-L-11081, Withdrawal of License Amendment Request 10-06, Request to Revise Technical Specification (TS) Sections 6.7.6.k, Steam Generator (SG) Program, and TS 6.8.1.7, Steam Generator Tube Inspection Report, for Temporary Alternate Repair Criteria

Withdrawal of License Amendment Request 10-06, Request to Revise Technical Specification (TS) Sections 6.7.6.k, Steam Generator (SG) Program, and TS 6.8.1.7, Steam Generator Tube Inspection Report, for Temporary Alternate Repair Criteria

ML11112A024
Person / Time
Site:	Seabrook
Issue date:	04/19/2011
From:	Freeman P NextEra Energy Seabrook
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SBK-L-11081
Download: ML11112A024 (2)

Text

NExTera April 19, 2011 SBK-L- 11081 Docket No. 50-443 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Seabrook Station Withdrawal of License Amendment Request 10-06 Request to Revise Technical Specification (TS) Sections 6.7.6.k, "Steam Generator (SG)

Program," and TS 6.8.1.7, "Steam Generator Tube Inspection Report,"

For Temporary Alternate Repair Criteria Reference NextEra Energy Seabrook, LLC letter SBK-L-10234, "License Amendment Request to Revise Technical Specification (TS) Sections 6.7.6.k, "Steam Generator (SG) Program,"

and TS 6.8.1.7, "Steam Generator Tube Inspection Report," for Temporary Alternate Repair Criteria," January 27, 2011 (ML110330202)

NextEra Energy Seabrook, LLC (NextEra) submitted License Amendment Request (LAR) 10-06 for an amendment to the Technical Specifications (TS) for Seabrook Station. The proposed change would revise TS 6.7.6.k, "Steam Generator (SG) Program," to exclude portions of the SG tubes below the top of the SG tubesheet from periodic inspections during refueling outage 14 (OR14) in the spring of 2011 and the subsequent inspection cycle. In addition, this amendment request proposed to revise TS 6.8.1.7 "Steam Generator Tube Inspection Report."

The requested amendment would have been required if primary water stress corrosion cracking (PWSCC) had been detected during the steam generator tube inspections in the April 2011 refueling outage. The inspections completed with no indications of PWSCC; therefore, NextEra is withdrawing LAR 10-06.

1400d NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874

United States Nuclear Regulatory Commission SBK-L-11081 Page 2 Should you have any questions regarding this letter, please contact Mr. Michael O'Keefe, Licensing Manager, at (603) 773-7745.

Sincerely, NextEra Energy Seabrook, LLC Paul Freeman Site Vice President cc: NRC Region I Administrator G. E. Miller, NRC Project Manager W. J. Raymond, NRC Senior Resident Inspector 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 Mr. John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399