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Category:Deficiency Report (per 10CFR50.55e and Part 21)
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[Table view] Category:Facsimile
MONTHYEARML12121A5132012-04-19019 April 2012 Interim Report of Evaluation of a Deviation Pursuant to 10 CFR 21.21(a)(2) 2012-04-19
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Text
04/19/2012 THU 13:06 FAX 703 908 8041 MNES U001/003
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04/19/2012 THU 13:06 FAX 703 908 8041 MNES U002/003 A
MITSUBISHI HEAVY INDUSTRIES, LTD.
U.S. Nuclear Regulatory Commission Ref: UET-20120105 Attn: Document Control Desk Date: Apr. 17, 2012 Washingtoni D 20555-0001 Subiect: Interim Report'of Evaluation of a Devlatlpnwiau*nt to 19 CFR 21.21(a)(2)
Mitsubishi Heavy Industries, =To (MHI) has Identified steam generator tube leak during first cycle after steam generator replacement.
The following information is provided pursuant to the requirements of 10 CFR 2l to submit an interim report on issues for which the evaluation will not be completed within 60 days of discovery.
An interim report on the evaluation, is attached; specifically; Interim Report No. U21 -01 9-1R1 Those MHI customers potentially affected by this Issue have been notified and will receive .acopy of:this Interim report.
Yours very tru!y,.
Ei Kadokami Senior Vice President Deputy Head of Nuclear Energy Systems Head of Kobe Shipyard & Machinery Works Mitsubishi Heavy Industries, Ltd.
04/19/2012 THU 13!06 FAX 703 908 8041 MNES 2003/003 Attachment to UET-201 20105 Interim Report U21-019-IR (0) 1~/1
Subject:
interim Report of evaluation pursuant to 10 CFR 21.21 (a) (2)
Title:
Steam Generator Tube Leak during First Cycle after Steam Generator Replacement (San Onofre 3)
Identification of Basic Component:
Replacement Steam Generators for San Onofre Nuclear Generating Statian Unit 3 Basic Component Supplied by:
Mitsoubishi1Heavy Industries.., LTD.
Nature of Deviation:
On January 31, 2012, San Onofre Unit 3 shut. down due to indications of a steam generator tube leak. Steam generaator tube inspections confirmed one small leak on one tube in one of the two steam generators. Continuing inspections of 100%
of the steam generator tubes in bo-th Unit 3 steam genierators discovere unexpected wear, including tube to tube as well as tube to tube support structural wear.
Inspection, testing, and analysis of SG tube integi'ty in both Unit 3 SGs is ongoing. In-situ pressure testing identif led eight Unit 3 SG tubes that did not meet the- target per~formance criteria In Technical Specificaiion for tube integrity. One of the failed tubes was the leaking, tube that required the Unit 3 shutdown.
DIscovery Date: February 21, 2012 Evaluation completion schedule date: August 31, 2012