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
[Table View] |
Text
STONE 6 WEBSTER ENGINEERING CORPORATION 245 SUMMER STREET, BOSTON. M ASS ACHUSETTS ADDRESS ALL CORRESPONDENCE TO P.O. SOK 2325. SOSTON. M ASS. 02107 SOST C Na t.UCTION NoustoN A ns ATIONS EI' '.".* *'"
N EE*IN$.T." 'oM Mr. Harold Denton January 3, 1980 Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
During the process of collecting pipe support loads for use in the IE Bulletin 79-02 Baseplate Evaluations, it came to our attention that some of the pipe supports on 2 1/2 to 6 inch piping on the Beaver Valley 1 Power Station are designed for loads that were derived from Shock 2 Computer calculations.
It had previously been thought that the calculations of record for these supports were simplified manual calculations.
In response to the telephone request by your Messrs. Wigginton and Wychman, we have obtained the following information with respect to the other projects that were affected by the March 13, 1979 Order to Show Cause:
Surry 1 and 2 No Shock 2 computer runs were identified in connection with 6 inch and under piping.
Maine Yankee
- There were a number of Shock 2 runs identified in connection sith 6 inch and under piping and all were reanalyzed as a part of the Show Cause reanalysis.
J. A. FitzPatrick-There were no Shock 2 runs identified in connection with 6 inch and under piping.
We do not believe that there are any safety implications from this finding since previous reanalysis of Shock 2 calculations did not result in any significant changes.
Very rul yo s,
g, g 5
rec t of inee ng lO 1708 015 80010904 M
-.