ML20202F338

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Provides Results of Util Voluntary Inspections on Plant Torus Wall Thickness Performed from 971210-31.Engineering Evaluation of Wall Thickness Determined It Would Not Adversely Affect Long Term Structural Integrity of Torus
ML20202F338
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 02/11/1998
From: Abney T
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9802190179
Download: ML20202F338 (4)


Text

{{#Wiki_filter:_ e IM Tennessee Vatey Authonty, Post Off.ce Bos 2000, Decatur. Alabama 35609 February 11, 1998 i U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen: In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND 3 - REQUEST FOR INFORMATION REGARDING TORUS WALL THICKNESS - TORUS INSPECTIONS I

SUMMARY

REPORT l f This letter provides the results of TVA's voluntary inspections on BFN's torus wall thickness. On December 23, 1997, in our response to the NRC staff's request for information regarding torus wall thickness, dated October 27, 1997, TVA agreed to voluntarily perform additional torus inspections on Units 1 and 2 to address the staff's concern on torus wall thinning from corrosion. TVA performed the additional inspections from December 10, 1997 to December 31, 1997 The scope of the inspections included ultrasonic [UT) examinations of torus bays to determine the Units 1 and 2 torus wall thickness. The UT examinations were conducted on the shell plates of each torus using qualified Level I and II nondestructive examiners in the vicinity of the torus-to-ring girder support welds, at the air-water interface, and in submerged areas. For each unit, plates in eight of the 16 torus bays were examined at the bottom of the torus, 10 and 15 feet from the bottom centerline weld on the bottom of the torus, and at the air-water interface. Altogether, TVA conducted a 100 percent UT scan on a total of 215, 12" x 12" inspection sites for each ) unit. l D 0 yS 4 m 9002190179 900211 g-{g'%.,%,~'yf.- PDR ADOCK 05000259 ,{, G PDR t

l e I l Huclear Regulatory Commission l Page 2 l February 11, 1998 The BrH Units 1 and 2_ torus bays were fabricated from carbon steel plate material-with a nominal plate thickness of.750".- ) The inside.and outside surfaces of the steel plates are coated.- As the UT examinations are conducted from outside the torus,- the initial UT readings for each insp9ction site included-only the plate and outside coating thickness of the torus. Inside coatings have no effect on the UT thickness measurements because the high acoustic impedance at the steel to coating interface on the inside surface of the torus causes most of the sound from the UT examinations to be reflected back from the interface. Since sound travels in coatings (i.e., paint) about three times slower than in steel, a dry film thickness correction factor for the outside surface coatings was calculated for each inspection site. This coating correction factor was then subtracted from the initial UT readings to obtain a net UT thickness reading of the torus steel plate. The UT examinations from the BFN Units 1 and 2 rorus inspections L indicated that torus wall thickness measurements in Units 1 and 2 -meet the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. Additionally, the UT examinations sevealed that,the protective coatings on the insf.de surfaces of the Units 1 and 2 torus wallsJare in good condition. Except for one location inLthe Unit 1 torus, the UT readings obtained from Units-1 and 2 exceeded the ASME Section XI, Subsection IWE criteria. The average minimum _ reading for all 430, 12" x 12" inspection locations that were UT scanned in Units 1 and 2, less their coatings, was.714" and.708", respec'tvely. In comparison, the average minimum UT reading for Unit 3 }erformed by the NRC E inspector on April 24 and 25, 1997, was .739". The NRC findings on the-Unit 3 torus wall thickness are documented in NRC Inspection Report 50-259/97-05, 50-260/97-05, and 50-296/97-05, TVA expected the average minimum UT readings for the three units at -BFN to be fairly close to each other. This is based not only on-the-similarities in operating history between the units but

o Nuclear Regulatory Commission Page 3 February 11, 1998 also on the torus inspection and protective coating program that TVA has established and maintained to prevent corrosion wall thinning. The lowest UT reading obtained on the Units 1 and 2 torus steel plate thickness was.670" and.686", respectively. The.670" reading, which was taken in the submerged area of Unit 1 torus-to-ring g3rder welds, is slightly below the 10 percent of nominal plate thickness allowance (.675") of Section XI, Subsection IWE of the ASME Code. This was the only UT reading that did not meet the ASME Code allowable wall thickness. Unit I has been shutdown and defueled since March 1985. It is currently on administrative hold with no plans for restart. However, TVA conducted a supplemental UT er. amination on Januar*] 2 6, 1998, and in addition, an engineering evaluation for the Unit 1 torus area that contained the.670" reading. UT examination revealed a gradual and very uniform change in wall thickness relative to the inside surface of the torus which was not indicative of pitting corrosion or an embedded flaw. This gradual uniform change in wa'.1 thickness appeared to be some type of anomaly associated with original fabrication (e.g., grinding) of the torus steel shell rather than corrosion. TVA's engineering evaluation of the.670" wall thickness determined it would not adversely affect the long term structural integrity f the torus. If you have any questions concerning this information, please contact me at (205) 729-2636. Sincerel' (* @ 4 Manager of Licene rg and Industry affairs cc: See page 4 _ a

U.S. Nuclear Regulatory Commission i Page 4 February 11, 1998 cc Mr. A. W. De Agazio, Project Manager. U.S. Nuclear Regulatory Commission One White Flint, North r 11555 Rockville Pike Rockville, Mary),and 20052 Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission 4 Region II 61 Forsyth Street, S.W. Suite 23T85 Atlanta, Georgia 30303 NRC Resident. Inspector Browns Ferry Nuclear Plant -10833 Shaw Road Athens, Alabama 35611 I i k 1 ti au ~, -_,p,-._ ~ r n,, ---,.m,m c,-}}