ML19211C546

LER 80-001/01T-0:on 790803, Rept on Seismic Reanalysis of Safety-Related Piping Sys,Rev Erroneously Stated No Piping Sys of Six Inches or Under Was Analyzed Using SHOCK-II.Nine Problems Actually Analyzed w/SHOCK-II

ML19211C546
Person / Time
Site:	Beaver Valley
Issue date:	01/04/1980
From:	Werling J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19211C542	List: ML19211C541 ML19211C546
References
LER-80-001-01T, LER-80-1-1T, NUDOCS 8001110661
Download: ML19211C546 (1)

Text

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D ATE EVENT OESCRIPTION AND PRO 8 ABLE CONSEQUENCES h og: lIt has been found that in the August 3, 1979 " Report On The Seismic Reanalyses Of l o 3 l Safety Felated Piping S'f3tems For Beaver Valley, Unit 1. Rev. ,

it was stated that l o 4 lno pipine systems of six inches (6") or under had been analyzed using the Sil0CK II j o s (procram. It was stated that these systems had been hand calculated. Since that l o le time, we have foiM that nine (9) nroblems have been run with Sil0CK II. These 1 o 7 fprollems are now being reanalyzed using the NUPIPE procram. l o a l I 7 8 9 80 SYSTEu CAUSE CAUSE COMP. VALVE CODE CCDE SUSCODE COMPONENT CODE SueCOCE aVOCCCE O 9 j 7. l 7 lh l A l@ l 8 lh l Z l Z l Z l 2 l Z l Z l@ l Z l@ l Z l @

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i ii [ problems and will identify additional modifications should any be necessarv. See l 7 l attached letter from Duquesne Linht Company Director of Nuclear Operations. [

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January 3, 1980 Director of Nuclear Reactor Ragulation United States Nuclear Regulatory Commission Attn: A. Schwencer, Chief Operating Reactors Branch No. 1 Division of Operating Reactors Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Seismic Reanalysis of Piping Systems

_ Gentlemen:

In our " Report on the Seismic Reanalyses of Safety Related Piping Systems for Beaver Valley, Unit No. 1", Revision 4, dated August 3, 1979, we stated that no piping systems of 6" or less in size had been analy:cd using a SHOCK II subroutine as the run of record. We stated in this report that all piping runs of these sizes had been hand calculated.

We have determined that this statement was not entirely correct.

A total of nine commiter problems have been fcund to exist for which the SHOCK II run is the run of record for some of the pipe supports included in these problems.

We are proceeding to reanaly e these problems using the NUPIPE co=puter progran. ,

We vill provide you with an update to the original report which will discuss the results of the reanalyses of these problems and will identify additional codifications, should any be determined to be necessary.

Sincerely,

[

J. J. Carey Director of Nuclear Operations Powcr Stations Department 33 :a 1742 042 e