ML063550199

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 Piping Connections at Pressurized-Water Reactors.

ML063550199
Person / Time
Site:	Braidwood
Issue date:	12/21/2006
From:	Coutu T Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BL-04-001, BW060117
Download: ML063550199 (4)

Text

______________Exel_nQ Exelon Generation Company LLC ww~v.exe1oncorp~com N uc]ear Braidwood Station~~O S~~t Erc~o~E~'8'~~17 O~O December 21, 2006 10 CFR 50.54 (f)BW060117 U.S.NuclearRegulatory Commission ATTN: DocumentControlDesk11555Rockvilie Pike Rockville, Maryland 20852 BraidwoodStation,Unit 2 Facility Operating License No.NPF-77NRCDocket No.STN 50-457

Subject:

Braidwood Station, Unit 2 60-Day Response to NRC Bulletin 2004-01,"Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and SteamSpacePiping 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 theFabricationof Pressurizer Penetrations andSteamSpacePiping Connections at Pressurized-Water Reactors."RequestedInformation Section 2(a)of this bulletin requires the following information be submiffed to the NRC within 60 days after plantrestartfollowing the next inspection oftheAlloy 82/182/600 pressurizer penetrations and steamspacepiping connections:

"...astatementindicating that the inspections described in thelicensee'sresponseto 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, tollowup NDE performed to characterize flaws in leaking penetrations or steamspacepiping connections, a summary of all relevant indications found by NDE, a summary of the disposition of any findings ofboricacid, and any corrective actions taken and/or repairs madeasa result of the indications found."Pursuantto 10 CFR 50.54,"Conditionsoflicenses,"

paragraph (f), Attachment 1 to this letter provides the Braidwood Station Unit 2 60-Day response.This response is due to theNRCby January 2, 2007.

December 21, 2006 U.S.NuclearRegulatory Commission Page 2 Please direct any questions you may have regarding this submittal to Mr.Dale Ambler, Regulatory AssuranceManager,at (815)417-2800.Ideclareunder penalty of perjury that the foregoing istrueand correct.Respectfully, Executed on 12/21/06________________________

Thomas Coutu Site Vice PresidentBraidwoodStation

Attachment:

BraidwoodStation Unit 2 60-Day Response to NRC Bulletin 2004-01 ATTACHMENT Braidwood Station Unit 2 60-Day Response to NRC Bulletin 2004-01"Inspection of Alloy 82/182/600 Materials Used in theFabricationof Pressurizer Penetrations and Steam SpacePipingConnections at Pressurized-Water Reactors" ATTACHMENTBraidwoodStation Unit 2 60-Day Response to NRC Bulletin 2004-01 On May 28, 2004, the NRC issued NRC Bulletin 2004-01,"Inspection of Alloy 82/182/600 Materials Used in theFabricationofPressurizerPenetrations andSteamSpacePiping Connections at Pressurized-Water Reactors."

This bulletin requires the following information be submitted to the NRC within 60 days afterplantrestart following the next inspection of the Alloy 82/182/600 pressurizer penetrations and steamspacepiping 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 ofthrough-wa//leakage,followupNDE performed to characterize flaws inleakingpenetrations or steam space piping connections, a summary of a/I relevantindicationsfound by NDE, a summary of the disposition of any findings of boric acid,andany corrective actions taken and/or repairs made as a result of the indications found."ResDonse Summary of the InspectionsPerformed,Extent of theInspections,andMethods Used During the Fall 2006 refueling outage (A2R12), a baremetalvisual(BMV)examination was performed on all five of the pressurizer steam space penetrations and adjacent pressurizer shellsurfaces.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)InspectionLocations,Implementation, and Inspection Guidelines,"

andER-AP-331-1002,"Boric Acid Corrosion Control Program Identification, Screening, and Evaluation."

The examination was performed after insulation was removedfromthetop of the pressurizer and the five associatedpenetrations.The examination was adirectvisual examination within two feet of the area of interest,ensuringany boric acid leakage would beeasilyidentified.

The full circumference of each of thefivepenetrations was examined.The examination was performed real time bycertifiedVT-2 examiners.

Description of the As-FoundCondition,Findings of Relevant Indications, and Summary of theDispositionofAny Findings The examination of thefivepenetrations 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 thefivepenetrations and adjacent pressurizer vessel surfaces, there was no follow up NDE, disposition of findings, or corrective actions required.Page 1 of 1