ML043520092
| ML043520092 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/13/2004 |
| From: | Joyce T Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BL-04-001, BW040108 | |
| Download: ML043520092 (4) | |
Text
Exekern.M Exelon Generation Company, LLC www.exeloncorp.com Nuclear Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 Tel. 815-417-2000 December 13, 2004 10 CFR 50.54 (f)
BW0401 08 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. STN 50-456
Subject:
Braidwood Station, Unit 1 Sixty-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 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."
Pursuant to 10 CFR 50.54, "Conditions of licenses,' paragraph (f), Attachment 1 to this letter provides the Braidwood Station, Unit 1 Sixty-Day response. This response is due to the NRC by December 22, 2004.
I 1
411o
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 IZ2 1t10X H
T. P. Joyce Site Vice President Braidwood Nuclear Generating Station
Enclosures:
Attachment, Braidwood Station Unit 1 Sixty-Day Response to NRC Bulletin 2004-01 cc:
Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Braidwood Station
ATTACHMENT Braidwood Station Unit 1 Sixty-Day Response to NRC Bulletin 2004-01
" Inspection of Alloy 821182/600 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 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."
Response
Summary of the Inspections Performed, Extent of the Inspections, and Methods Used During Al Ri 1 (Fall 2004 refuel outage), a bare metal visual (BMV) examination was performed on all five of the pressurizer steam space penetrations and adjacent pressurizer shell surfaces. The examination was conducted in accordance with Exelon corporate procedures ER-AA-335-015, 'ST-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.
All five penetrations were examined 360 degrees around. The examination was performed real time by certified VT-2 examiners.
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 vessel 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.