ML19263D930

Responds to 781201 Memo Re BNL Status Rept on Incoloy 800H. Based on Review of Insp Repts,Concludes There Is Reasonable Assurance That Proper Grades of Incoloy 800 Were Used in Plant Reactor

ML19263D930
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/23/1979
From:	Harold Denton Office of Nuclear Reactor Regulation
To:	Levine S NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
Shared Package
ML19263D922	List: ML19263D921 ML19263D924 ML19263D927 ML19263D930
References
NUDOCS 7904170069
Download: ML19263D930 (2)

Text

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IRNR5iDUM IOR:

Saul f.evine. Director,' Office of 0:uclear Regulatory

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J Harold R. Denton, Director,' Office of nuclear Reactor 3

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.'.v: :.' Regulation'...: *

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n USE OF II!COLOY 800 Ill FORf Sf. VRAlil SIE/J1 GE!H:RATCP,5

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SUBJECT:

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.In youF acuorandum of Deccaber.'1,19/8, " Status Report on facoloy C00!i,"-

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you t.ransmitted a ieport prepa' red by Brookhaven rational I.aboratory dated p

' Septcmber 6,19/8 pertaining.to concerns about the use of Incoloy 800.in

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.the rort St. Vrain. stet:a generators.

Also, you reco. mended that a review

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. of quality assurance procedures sheuld he unde to detemine that cc.:plet<2

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inspection of _ the.Incoloy compenents for adequ' ate grain size is prcvided.

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He have revieued bothithe FSAR and reperts frca the inspectces of the then 17 Division of Compliance, Region IV.. lie find that the FSAR recognized the use of Grade 2. for high temperature colponents, particularly the support

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structure for reheater and superheater tubing (FS/R Tc.bic 4.2-3).

!!c also find that the Division.of,Cmpliance investigated quality assurance procedures to assure that an acceptably large grain size should be found for Grade 2 natorial.

A sumary of these Compliance: reports follous. -

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_A four day inspection visit Iraa January 12 through 16,19/0 t;as n'ade of the General Iron Ucrks plant in Denver, Colorado, with a report of the-inspectial forwarded by John W. Flora to J. P. O'Reilly on fiarch 6,.1970.

The tem reported 'that the lii-Fe-Cr pressure tubing (called Sanicrch31, but' essentially. Incoloy 300) supplied by Sandvik satisfied all the ;.

requirements of General Atemic's aanufacturing specifications, including

'.,l grade checking by meta!1cgraphic exe.aination for grain size.

Sulzer was y.-

• contracted by GA to perform the quality assurance function cn all Sandvik supplied tubing...The. March G report also stated that "several Sulzer.

reports were reviev;ed and found.to be very detailed and comprehensiv_,

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e indicating excellent quality control."

A problea, houever, was found with soma of the Incolay 800 plate material used for the tubing suppcrt structures utde by the General fron Ucrks.

In one case the plate raterial had' been ordered and fchricated as Grade 1 and later reheated by solution annealing to convert the structure to Grade 2.

.c-Ca investigation the inspectors found that scme questions remained en certifications of the various plate materials received and on the heat

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I j treatment proccdure of the structure recancaico.

A folloit-up report s

(J. P. O'Reilly i.o P,. S. Coyd, l'ey 22,1970) stated that the solution annealing process ves to be dupliccted using a spcre cc c,r:c;unt to deaonstrate the cdequacy of the heat treatment. Th2 report also stated that recertificatica of ti;e Incoloy plate mterial, supplied frca three different vendors, was in progress.

On August 13, 1970 a report uas transmitted froa John 11. Flera to Jecas P. O'Peilly 1:hore it was stated that the resolutlen annealing of support structure cc:rpo.1ests.;5' had been duplicated.

Specinens fre'a various creas of the heat treated components unre e;:ainined metallurg!cally with the conclusion that

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... a satisfactory solution annealed condition hed bctn obtai::ed

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throughout the structure."

It was also reperted that,the recertificatica progrcia had been cor.ipleted.-

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Based on our review of the inspection rcports referenced above we conclude-,,' '

that there is reasonable assurance t. at the proper grades of Incoloy 600 vare used in the Fort St. Vrain reactor.

1:e do not believe it is necessary to further review tin quality assuccoce procedures related to this s

• investigation or, e, recomended by Crochhaven, re-evaluate the data base used to design the Fort St. Vrain stear.) generator.

gD CQ...': Q-- ! by H. iT. D:,un liarold R. Danten, Director Of fice of !!uclear Reactor regulation s

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