ML20011A674

Interim Deficiency Rept Re Sensitized Stainless Steel Pipe Spools,Initially Reported 810924.Unit 2 Spools Have Been Corrected.Evaluation of Unit 1 Spools Continuing.Final Rept Will Be Submitted by 820115

ML20011A674
Person / Time
Site:	Perry
Issue date:	10/22/1981
From:	Davidson D CLEVELAND ELECTRIC ILLUMINATING CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8110290272
Download: ML20011A674 (2)

Text

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THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY P O. BOX E000 m CLEVELAND, OHlo 44101 e TELEPHONE (216) 622-9800 m (LLUMINATING O' OG. e 55 PUBLIC SC' AE Dalwyn R. Davidson So vicTT 4 .e Best Location in the Nation

,- nn x VICE PRESIDENT e' d /

SYSTEM ENGINEERING AND CONSTRU"!'ON October 22,19814) ,

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OCT '> ' ' Eb '

Mr. James G. Keppler Director .f Region III o ,, , 4 3 gO/ A .

Office of Inspection sad Enforcement "'*

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U. S. Nuclear Regulatory Commission (,

799 Roosevelt Road /

Glen Ellyn, Illinois 60137 ' i * :9 ' e RE: Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Interim Report on Three (3)

Sersitized Stainless Steel Pipe Spools (RDC 38(81))

Dear Mr. Keppler:

This letter serves as an Interim Report as required by 10CFR50.55(e) concerning three (3) stainless steel piping sub-assemblies containing spool pieces that had been bent hot without benefit of subsequent solution annealing. This was first reported by W. J. Kacer of The Cleveland Electric Illuminating Company to L. McGregor of your of fice on September 24, 1981.

This report includes a description of the deficiency, the corrective action completed to date and the planned method for completion of evaluation.

DESCRIPTION OF DEFICIENCY Two ten-inch diameter, schedule 10, stainless steel piping spools were identified in the installation contractor's l aydown area as being nonconforming due to surface corrosion. Upon further investigation by the fabricator and the Perry Project Organization, it was discovered that the spools were not solution heat treated after hot bending and in addition, the fabricator also identified a third stainless steel spool piece presently installed in Unit I that has similar thermal history. The Unit I spool is ten-inch diameter, schedule 40.

The above material was furnished under Pullman Power Products' contract (SP-527) for the fabrication and delivery of safety-class piping.

CORRECTIVE ACTION TAKEN A corrective action request (CAR 015) has been issued to document that Pullman Power Products was not carbide solution heat treated and water quenched hot bent and incre-ment bent stainless steel piping as required. No further shipments of piping were made from Pullman Power Products until the corrective action response was received and evaluated for acceptability. Pullman Power Products' response to the corrective action request has been accepted and closed out, tof a rgoggjlaggh g OCT 2 6 19 81 s .a M

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Mr. James G. Keppler.

October 22,-1981 Page Two The two Unit II. spools were returned'to the fabricator for' solution heat treating, pickling, passivating and liquid penetrant testing: of- the bend areas. This work was

' performed in accordance with' approved procedures and witnessed.by our msnufacturing' Lsurveillance quality specialist who performs. inspection activities in Pullman Power

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Products shop..

Pullman Power' Products' Authorized Nuclear Inspector reissued a Code. Data Report after all material was reviewed ard accepted. Documentation of the necessary activities

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was obtained and incorporated in the document packages.for these spools. The. spools have subsequently been delivered to the site for installation.

The two Unit . II spools, schedule 10, have been returned to an. annealed condition such that the safety of the plant will not be affected.

COMPLETION OF EVALUATION The Unit I spool, schedule 40,-18 completely embedded in concrete.' The spool is in theLFuel-Pool Cooling System. - It connects to the stainless' steel liner in theibottom '

of the reactor cavity pool and functions as a drain and. fill for the pool.

Extensive evaluation is required to determine if the condition exists in the area of the spool to promote detrimental corrosion. Given that such corrosiom can occur, an analysis is required to determine if the safety of the plant would be affected.

A minimum of two months for this ' analysis and final disposition of this' spool is estimated to be required and we are presently planning to submit our final-report on this problem by January 15, 1982.

Sincerely, THE CLEVELAND ELECTRIC ILLUMINATING COMPANY-Dalwyn R. Davidson, Vi e President System Engineering and Construction f

DRD/llp cc: NRC Site Office Mr. Victor Stello, Director Of fice of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. .20555 ,

U. S. Nuclear ~ Regulatory Commission c/o Document Management Branch Washington', D. C. 20555