ML19250D089

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Updates 800930 Memo Re Need for Multifrequency Eddy Current Insp Using Rotating Pancake Coil at Facility.Supplemental Insps Are Not Required
ML19250D089
Person / Time
Site: Arkansas Nuclear 
Issue date: 02/18/1981
From: Noonan V
Office of Nuclear Reactor Regulation
To: Novak T
Office of Nuclear Reactor Regulation
References
NUDOCS 8103050470
Download: ML19250D089 (2)


Text

{{#Wiki_filter:- M bV j ,-,,, o u S A FEB 1 3 Sd1 4 ~~. . ~ ~. A. "EMORANDUM FOR: Thomas W. Novak, Assistant Director Q C S,9 /Sg y ~.; N 0 for Operating Reactors E4Q. g% g Aj, Division of Licensing FROM: V. S. Noonan, Assistant Director 1 j y, for Materials and Qualifications Engineering sif g Division of Engineering

SUBJECT:

ARKANSAS UNIT 1 STEAM GENERATORS - ASSESSMENT OF NEED TO PERFORM MULTIFREQUENCY EDDY C'JRRENT INSPECTICH USING ROTATING PANCAKE COIL In a September 30, 1980 memorandum, V. S. Noonan to T. M. Novak, we recomended that the licensee ( Arkansas Power and Light) be requested to corniit to suppler nting its nomal ECT steam generator tube inspection proaram during the next inspection outage at Arkansas Unit I with additional inspections involving the use of multifrecuency ECT and a non-standard probe type with enhanced capability to detect circumfer-entially oriented tube flaws. The recorrendation developed as a result of the probable circumferential orientation of a fatigue crack which the licensee believes to be the cause of the tube leak occurrence Septeaber 1980, and our concerns regarding the ECT detectability of such flaws using single frecuency technicues and a standard (bobbin type) probe. A previous leak occurrence in July 1980 (less than two months earlier) effected a tube located adjacent to the tube which developed the September leak. However, no indication other than a distorted tubesheet signal was observed during ECT inspections perfemed during the July repair outage for the tube which later developed the September leak. Based upon further investigation into this matter includir,g a review of pertinent cperating experience at the Oconee units which have experienced 13 leaks due to circumferential fatigue cracks, we believe that the recent tube leak occurrences at Arkansas Unit 1, which are possibly fatigue crack related, do not represent a significant safety concern at this time. Even if circumferential fatigue cracks go undetected, there renains adequate assurance for safe operation. We conclude that there is no compelling safety reason at this time to recuire that the supple-mental tube inspections be perfomed. Nor is it clear that such inspec-tions would necessarily be effective in reducing the probability of future leak occurrences caused by circumferential cracks propagated by fatigue as a result of flow induced vibration. However, if leaks due to this phenomenon continue to occur at a high rate, remedial measures similar to those implemented at the Oconee units may become necessary. DISTRIBUT!ON Occket file 50-313 "TE3 Reading V. S. Noonan, Assistant Director ~ for Materials and nualifications Encineering

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