ML20207E371

Forwards SER Accepting Topic Rept SL-5159(P), Methodology & Verification of Gapp Program for Analysis of Piping Systems with E-Bar Supports, Submitted by Sargent & Lundy by Ltr

ML20207E371
Person / Time
Issue date:	03/02/1999
From:	Frank Akstulewicz NRC (Affiliation Not Assigned)
To:	Pressburger M SARGENT & LUNDY, INC.
Shared Package
ML20207E377	List: ML20207E371 ML20207E382
References
TAC-MA0227, TAC-MA227, NUDOCS 9903100249
Download: ML20207E371 (2)

Text

. - . .

4 AC CIO(f D

t UNITED STATES 7 E NUCLEAR REGULATORY COMMISSION-f WASHINGTON, D.C. 20 % 5-0001 March 2, 1999 Mr. Maury A. Pressburger Sargent and Lundy, L.L.C.

55 Fact Monroe St.

Chicago Illinois 60603

SUBJECT:

SAFETY EVALUATION RELATED TO TOPICAL REPORT SL-5159 (P),

" METHODOLOGY AND VERIFICATION OF THE GAPP PROGRAM FOR ANALYSIS OF PlPING SYSTEMS WITH E-BAR SUPPORTS." (TAC NO.

MA0227)

Dear Mr. Pressburger:

The staff has completed its review of the subject report submitted by Sargent & Lundy (S&L),

letter dated November 7,1997. The staff has found that this report is acceptable for referencing in licensing applications or licensee modifications made pursuant to 10 CFR 50.59, to the extent specified and under the conditions for applicability delineated in the associated NRC safety evaluation (SE), which is enclosed. The SE also defines the basis for acceptance of the report.

The staff will not repeat its review of the matters described in S&L Topical Report SL-5159P, when the report appears as a reference in license applications, except to ensure that the material presented applies to the specific plant involved. In accordance with procedures established in NUREG-0390, the NRC requests that S&L publish revised versions of the I submittal, proprietary and non-proprietary, within three months of receipt of this letter. As j discussed in the teleconference of February 22,1999, the revised versions shall incorporate this l letter and the enclosed SE between the title page and the abstract and an -A (designating accepted) following the report identification symbol.

If the NRC's criteria or regulations change so that its conclusion that the submittal is acceptable I are invalidated, S&L and/or the applicant referencing the topical report will be expected to revise l and resubmit its respective documentation, or submit justification for the continued applicability 1 of the topical report without revision of the respective documentation.

If you have specific questions regarding the enclosed SE, please contact Dr. Mark Hartzman of the Mechanical Engineering Branch at 301-415-2755.

Si . erely, e*

ll . . >

^W 'y jl ank M. A fu ewicz, Acting Chief

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n o a' {' 1 Generic issues and Environmental Branch Division of Regulatory improvement Programs 6 C)}

Office of Nuclear Reactor Regulation

Enclosure:

Topical Report Evaluation O M 9903100249 990302 hD~N 0)AN ~)' l i

PDR TOPRP EECSALE C PDR .

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J Msrch' 2,/1999.-

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Mr. M ury A; Pr,::ssburger5 ,

F Sargent'and Lundy[L.LC.

155 East Monroe St.

I Chicago, Illinois 60603.

l

SUBJECT:

l SAFETY EVALUATION RELATED TO TOPICAL REPORT SL~-5159 '(P), .

" METHODOLOGY AND VERIFICATION OF THE GAPP PROGRAM FOR 1 E ANALYSIS OF PIPING SYSTEMS WITH E-BAR SUPPORTS." (TAC NOf l

[

4 MA0227)

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Dear Mr. Pressburger:

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(

The staff has completed its review of.the subject report submitted by Sargent & Lundy (S&L)l.

l j- letter dated November 7,1997. The staff has found that this report is acceptabl.e for referencing in licensing applications or licensee modifications made pursuant to 10 CFR 50.59, to the extent l ~

specified and under the conditions for applicability delineated in the associated NRC safety L evaluation (SE) which is enclosed. The SE also defines the basis for acceptance of the report.

The staff will not repeat its review of the matters described in S&L Topical Report SL-5159P, when the report appears as a reference in license applications, except to ensure that the material presented applies to the specific plant involved. In accordance with procedures established in NUREG-0390, the NRC requests that S&L publish accepted versions of the submittal, proprietary and non-proprietary, within three months of receipt of this letter.- The -

accepted versions shall incorporate this letter and the enclosed SE between the title page and the abstract and an -A (designating accepted) following the report identification . symbol.

If the NRC's criteria or regulations change so that its conclusion that the submittalis acceptable ,

are invalidated, S&L and/or the applicant referencing the topical report will be expected to revise and resubmit its respective documentation, or submit justification for the continued applicability j of the topical report without revision of the respective documentation. .

If you have specific questions regarding the enclosed SE, please contact Dr. Mark Hartzman of the Mechanical Engineering Branch at 301-415-2755.  ;

Sincerely, Original'Sfaned B Frank M. Akstdlewicz,y: Acting Chief Generic issues and Environmental Branch

~

Division of Regulatory improvement Programs Office of Nuclear Reactor. Regulation .

Enclosure:

Topical Report Evaluation Distribution:cen6erfile PUBLIC EMEB RF DE RF OGC ACRS

' DOCUMENT NAME: G:\HARTZMAN\EBARSE3 WPD ,

To receive a copy of this document, indicate in the box C= Copy w/o attachment / ATTACHMENT E= Copy with -

attachment / ATTACHMENT N = No copy *See Previous Concurrences i ,

.omcE EMEB.DE - EMEB:DE EMEB:DE ' ' Dd:dE' PM PGEB (f ( .1 A 'I NAME MHartzman* JFair' KManoly' 'RWessman*' JBirmingham l FMatulewicz DATE 2/3/99I 2/25/99 I 2/25/99 ' 2/28/99 4 / / 199 3 /N LOFFICIAL RECORD copy e . ,g ,

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