ML051880063
| ML051880063 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/28/2005 |
| From: | Warner M Florida Power & Light Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BL-04-001, SBK-L-05130 | |
| Download: ML051880063 (5) | |
Text
FPL Energy Seabrook Station FPL Energy P.O. Box 300 Seabrook, NH 03874 Seabrook Station (603) 773-7000 JUN 2 8 2005 Docket No. 50-443 SBK-L-05130 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 - 0001
Reference:
Florida Power and Light Company, Letter L-2004-160, "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 July 27, 2004 Seabrook Station Response to NRC Bulletin 2004-01, Request 2, 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," FPL Energy Seabrook, LLC (FPL Energy Seabrook) submits the enclosed response to Bulletin 2004-01, Request 2. The enclosed report details the inspection of Alloy 82/182/600 materials required by the bulletin and is being submitted within 60 days of plant restart from refueling outage OR1 0 on May 3, 2005.
Should you require further information regarding this submittal, please contact Mr. James M.
Peschel, Regulatory Programs Manager, at (603) 773-7194.
Very truly yours, FPL Energy Seabrook, LLC Mark E. Warner Site Vice President 4V(ID an FPL Group company
U. S. Nuclear Regulatory Commission SBK-L-05130/Page 2 cc:
S. J. Collins, NRC Region I Administrator V. Nerses, NRC Project Manager, Project Directorate 1-2 G. T. Dentel, NRC Senior Resident Inspector OATH AND AFFIRMATION I, Gene F. St.Pierre, Station Director for FPL Energy Seabrook, LLC, hereby affirm that the information and statements contained within this response to NRC Bulletin 2004-01 are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.
Sworn and Subscribed before me this
___2j9 day of J (4r ae-
,2005 Gene F. St.Pierre Station Director Notary Public~~
-.FEB.
5, 2008 r
ENCLOSURE TO SBK-L-05130
NRC Bulletin 2004-01 Sixty (60) Day Report FPL Energy Seabrook submits this report pursuant to NRC Bulletin 2004-01, Inspection ofAlloy 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 OR10 on May 3, 2005.
Paragraph 2 (a) 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 performed 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), FPLE 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.
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 was performed.
Extent of Examination A 3600 visual examination, using VT-2 visual examination criteria, of 6 Pressurizer Alloy 82/182 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 ASME Section XI near distance vision test chart for VT-2 examination.
As-Found Condition None of the 6 Pressurizer Alloy 82/182 piping connections exhibited evidence of pressure boundary leakage. Two of the steam space nozzles appeared to have previous liquid penetrant developer remaining in the toes of the nozzle welds in a few locations.
Disposition of Developer Indication As required by the FPLE Seabrook work plan, indeterminate visual indications receive liquid penetrant examination. Liquid penetrant examination was performed on the two steam space nozzles and results were acceptable.
Corrective Actions as a Result of Indications No corrective actions were required. No evidence of pressure boundary leakage was observed.