ML061640450

Day Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Connections at Pressurized-Water Reactors

ML061640450
Person / Time
Site:	Braidwood
Issue date:	06/12/2006
From:	Polson K Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BL-04-001, BW060058
Download: ML061640450 (4)

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June 12, 2006 10 CFR 50~54(f)

BW060058 United States Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, Maryland 20852 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No. SIN 50-456

Subject:

Braidwood Station, Unit 1 60-Day Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Connections at Pressurized-Water Reactors On May 28, 2004, the NRC issued NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Connections at Pressurized-Water Reactors~Requested Information section 2(a) of this bulletin requires the following information be submitted to the NRC within 60 days after plant restart following the next inspection of the Alloy 82/182/600 pressurizer penetrations and steam space piping connections:

...a statement indicating that the inspections described in the licensees 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 foundS Pursuant to 10 CFR 50.54, Conditions of licenses, paragraph (f), Attachment ito this letter provides the Braidwood Station, Unit 1 60-Day response. This response is due to the NRC by July 2, 2006.

June 12, 2006 United States Nuclear Regulatory Commission Page 2 Please direct any questions you may have regarding this submittal to Mr. Dale Ambler, Regulatory Assurance Manager, at (815) 417-2800.

I declare under penalty of perjury that the foregoing is true and correct.

Respectfully, Executed on

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Keith J. Poison Site Vice President Braidwood Nuclear Generating Station

Attachment:

Braidwood Station Unit 1 60-Day Response to NRC Bulletin 2004-01

ATTACHMENT Braidwood Station Unit 1 60-Day Response to NRC Bulletin 2004-01 Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Connections at Pressurized-Water Reactors

On May 28, 2004, the NRC issued NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Connections at Pressurized-Water Reactors. This bulletin requires the following information be submitted to the NRC within 60 days after plant restart following the next inspection of the Alloy 82/182/600 pressurizer penetrations and steam space piping connections:

...a statement indicating that the inspections described in the licensees 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, foiowup NDE performed to characterize flaws in leaking penetrations orsteam 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.

Resionse Summary of the Inspections Performed, Extent of the Inspections, and Methods Used During Al R12 (April 2006 refueling outage), a bare metal visual (BMV) examination was performed on all five of the Braidwood Station Unit 1 pressurizer steam space penetrations and adjacent pressurizer shell surfaces. The examination was conducted in accordance with Exelon corporate procedures ER-AA-335-01 5, VT-2 Examination, ER-AP-331 -1001, Boric Acid Corrosion Control (BACC) Inspection Locations, Implementation, and Inspection Guidelines, and ER-AP-331-1002, Boric Acid Corrosion Control Program Identification, Assessment, and Evaluation.

The examination was performed after insulation was removed from the top of the pressurizer and the five associated penetrations. The examination was a direct visual examination within two feet of the area of interest, ensuring any boric acid leakage would be easily identified.

The full circumference of each of the five penetrations was examined. The examination was performed real time by a certified VT-2 examiner.

Description of the As-Found Condition, Findings of Relevant Indications, and Summary of the Disposition of any Findings The examination of the five penetrations and adjacent pressurizer shell surfaces identified no evidence of any boric acid deposits associated with reactor coolant leakage.

Corrective Actions Taken Based on the acceptable as found condition of the five penetrations and adjacent pressurizer vessel surfaces, there was no followup NDE, disposition of findings or corrective actions required.