Letter Sequence Other |
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Results
Other: ML19211C502, ML19225C629, ML19241B277, ML19242B871, ML19257A933, ML19274F296, ML19337A164, ML19351E408, ML20003H527, ML20008E280, ML20010A331, ML20030B943, ML20126H318
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MONTHYEARML19241B2771979-07-11011 July 1979
Forwards Revision 1 to Rept on Reanalysis of Safety-Related Piping Sys. Seven Piping Supports Will Be Modified & Two New Supports Will Be Installed.Requests Authorization to Begin Interim Operation Until Refueling
Project stage: Other
ML19274F2961979-07-18018 July 1979
Forwards Revision 2 to Rept on Reanalysis at Safety- Related Piping Sys
Project stage: Other
ML19225C6291979-07-27027 July 1979
Forwards Revision 3 to Rept on Reanalysis of Safety-Related Piping Sys. Change Reflects up-to-date Reanalysis & Mod Program
Project stage: Other
ML19242B8711979-08-0707 August 1979
Forwards Revision 4 to Rept on Reanalysis of Safety-Related Piping Sys
Project stage: Other
ML19257A9331980-01-0303 January 1980
Advises That Baseplate Evaluations Per IE Bulletin 79-02 Revealed Two & One half-inch to six-inch Piping Designed for Loads Derived from SHOCK-2 Computer Calculations
Project stage: Other
ML19211C5021980-01-0303 January 1980
Submits Corrections to 790803 Rept on Seismic Reanalyses of Safety-Related Piping Sys, Revision 4.Nine Computer Problems Exist for Which SHOCK-II Run Is Run of Record for Some Pipe Supports.Reanalyzing Problem
Project stage: Other
ML19337A1641980-08-14014 August 1980
Forwards Responses to IE Bulletin 79-14 & Suppls 1 & 2, Seismic Analysis for As-Built Safety-Related Piping Sys. W/Completion of Mods,All Piping Sys Will Be Able to Perform Required Safety Functions During Seismic Event
Project stage: Other
ML19331C6601980-08-14014 August 1980
Interim Deficiency Rept Re Linear Indications in Gib Gusset Welds in Reactor Vessel Structural Support(Neutron Shield Tank).Metallographic Analysis of Weld Samples & Addl Insps Being Conducted.Next Rept Will Be Issued on 801101
Project stage: Request
ML20008E2801980-10-20020 October 1980
Identifies Status of Activities Re IE Bulletin 79-14.All Physical Insp of Piping & QC Records Completed.All Piping Reanalyzed.Mods to Supports to Be Completed Before Startup. Requests Extension Until 810331 for Full Completion
Project stage: Other
ML19339A1831980-10-20020 October 1980
Amend 34 to License DPR-66,removing Nine Hydraulic Snubbers from Table 3.7-4 of Tech Specs
Project stage: Request
ML19351E4081980-11-0303 November 1980
Immediate Action Ltr 80-43:discusses Util 800814,0911 & 1020 Ltrs Re IE Bulletin 79-14.Enumerates Actions Taken or Planned by Util.Requests Response If Actions Differ from Actions Described
Project stage: Other
ML20126H3181981-03-31031 March 1981
Requests Extension Until 810407 for Submittal of Final Rept Re IE Bulletin 79-14, Seismic Analysis for As-Built Safety- Related Piping Sys. Addl Time Required for Review of Info Re Reanalysis Effort Supplied by Ae
Project stage: Other
ML20003H5271981-04-0707 April 1981
Submits Rept Re IE Bulletin 79-14, Seismic Analysis for As- Built Safety-Related Piping Sys. Rept Not Final Since Equipment Nozzle Info Is Incomplete.Vendor Responses Outstanding
Project stage: Other
ML20010A3311981-07-31031 July 1981
Requests 2-wk Extension to Satisfy Requirements of IE Bulletin 79-14,per .Util Awaiting Vendor Concurrence for Seven Components
Project stage: Other
ML20030B9431981-08-14014 August 1981
Submits Final Response to IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Sys. Nozzle Load Evaluations Complete & Required Mods Installed,Except for Two Items.Status of Equipment Nozzles Encl
Project stage: Other
1980-10-20
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e January 3, 1980 Director of Nuclear Reactor Regulation 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 $tation, 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 analyzed 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 computer problems have been found 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 reanalyze these problems using the NUPIPE computer program.
We will provide you with an update to the original report which will discuss the results of the reanalyses of these problems and will identify additional modifications, should any be determined to be necessary.
Sincerely, r
[G J. J. Ca re;-
Directar of Nuclear Operations Power Stations Department JJC:krg
/hg 1742 006 TD 1
8001770 5.39