ML070100538

Seabrook - NRC Bulletin 2004-01, OR11, Inspection of Alloy 82/182/600 Materials 60-Day Report

ML070100538
Person / Time
Site:	Seabrook
Issue date:	01/04/2007
From:	St.Pierre G Florida Power & Light Energy Seabrook
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BL-04-001, SBK-L-07002
Download: ML070100538 (5)

Text

FPL Energy Seabrook Station FPL~nergy O. Box 300 Seabrook, NH 03874 Sea brook Station (603) 773-7000 January 4, 2007 Docket No. 50-443 SBK-L-07002 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 -0001

Reference:

Florida Power and Light Company, Letter L-2005-01 1, "NRC Bulletin 2004-01, Request for Additional Information, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors," dated January 18, 2005 Seabrook Station NRC Bulletin 2004-01, ORi 1 Inspection of Alloy 82/182/600 Materials 60-Day Report Pursuant to NRC Bulletin 2004-01, "Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors," dated May 28, 2004, FPL Energy Seabrook, LLC (FPL Energy Seabrook)submits the enclosed report. This report is being submitted within (60) days of plant restart frQm refueling outage ORI 1 on November 10, 2006. In the referenced letter, FPL Enery Seabrook committed to perform bare metal visual (BMV) inspections of alloy 600/82/182 butt welds on the pressurizer each refueling outage. This commitment will exist until such time that EPRI, ASME, or the Commission issues guidance on inspection frequencies.

an FPL Group company I61. S. Nuclear Regulatory Commission SBK-L-07002/Page 2 Should you require further informnation regarding this submittal, please contact Mr. James M.Peschel, Regulatory Programs Manager, at (603) 773-7194.Very truly yours, FPL Energy Seabrook, LLC Gene St. Pierre Site Vice President cc: S. J. Collins, NRC Region I Administrator G. E. Miller, NRC Project Manager, Project Directorate 1-2 G. T. Dentel, NRC Senior Resident Inspector ENCLOSURE TO SBK-L-07002 NRC Bulletin 2004-01 Sixty (60) Day Report For Refueling Outage ORlII FPL Energy Seabrook submits this report pursuant to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors dated May 28, 2004.This report is being submitted within (60) days of plant restart from refueling outage ORIlI on November 10, 2006.Paragraph 2 in Requested Information of Bulletin 2004-01 states in part, within 60 days of plant restart following the next inspection of the Alloy 82/182/600 pressurizer penetrations and steam space piping connections, the subject PWR licensees should: (a) submit to the NRC a statement indicating that the inspections described in the licensee's response to item (1)(c) of this bulletin were completed and a description of the as-found condition of the pressurizer shell, any findings of relevant indications of through-wall leakage, followup, NDE performned to characterize flaws in leaking penetrations or steam space piping connections, a summary of all relevant indications found by NDE, a summary of the disposition of any findings of boric acid , and any.corrective actions taken and/or repairs made as a result of the indications found.In response to paragraph (1)(c), FPL Energy Seabrook committed to perform a 100% bare metal visual (BMV) examination (VT-2) on five (5) steam space nozzles and one (1)surge nozzle on the pressurizer, which possess alloy 82/182 weld metal.Additionally, on November 18, 2004, the NRC issued RAILs to FPL Energy Seabrook's response to NRC Bulletin 2004-01. In response to RAIL 1, FPLE Seabrook committed to perform bare metal visual (BMV) inspections of alloy 600/82/182 butt welds on the pressurizer each refueling outage. This commitment will exist until such time that EPRI, ASME, or the regulator issues guidance on inspection frequencies.

Inspection Performed A bare metal visual (BMV) examination (VT-2) of each (5) steam space piping connection and (1) surge line piping connection to the pressurizer at the alloy 82/182 butt weld was performed.

Extent of Examination A 3600 visual examination, using VT-2 visual examination criteria, of (6) pressurizer alloy 82/1 82 piping connections looking for evidence of pressure boundary leakage.

inspection Method A direct VT-2 visual examination was performed using certified VT-2 examiners.

Supplemental lighting was used to highlight areas of interest.

Illumination was verified for the direct visual examination at maximum working distance.

Verification was made using an ASMIE Section XI near distance vision test chart for VT-2 examination.

As-Found Condition None of the (6) alloy 82/182 piping connections on the pressurizer exhibited evidence of pressure boundary leakage.Corrective Actions No corrective actions were required.

No evidence of pressure boundary leakage was observed.