ML17250A587: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:IIestinghoose Electric Corporation I Nater Reactor Divisions Nuclear Technology Oivision Box 355 Pittsburgh Pennsylvania 15230 July 18, 1980 ST-SST-108 RGE-80-95 Mr.M.P.Li lley.Rochester Gas 8 Electric J9 East Avenue Rochester, Hew York 14649  
{{#Wiki_filter:I IIestinghoose             Nater Reactor                                 Nuclear Technology Oivision Electric Corporation      Divisions                                    Box 355 Pittsburgh Pennsylvania 15230 July 18, 1980 ST-SST- 108 RGE 95 Mr. M. P. Li lley
. Rochester Gas 8 Electric J9 East Avenue Rochester, Hew York             14649


==Dear Mr.Li lley:==
==Dear Mr. Li lley:==
ROBERT EMMETT GINHA NUCLEAR GENERATING STATION R, E.Ginna Seismic Upgrading Program Main Steam Stress Re ort Transmitted herein is the piping stress report for the'R.E.Ginna Nuclear Generating Station Unit No.1 Main Steam System, Section 200, SDTAR-80-05-'08..
 
Analysis results and support loads contained herein reflect the layout arrangement shown on marked isometric C-381-350, Sheet 1, Revision C.Any significant modifications to the layout of this system of piping and or its restraints will warrant reanalysis of this piping system.Minor design changes or construe.ion modifications will generally not affect stress results'and suppor t recottrtendations.
ROBERT EMMETT GINHA NUCLEAR GENERATING STATION R, E. Ginna Seismic Upgrading Program Main Steam Stress Re ort Transmitted herein is the piping stress report for the'R. E. Ginna Nuclear Generating Station Unit No. 1 Main Steam System, Section 200, SDTAR-80-05-'08..
However, case by case review of the discrepancies can be used to determine overall system behavior and effects.If any questions exist relative to the abo've transmittal, please contact W.A.Massie of Westinghouse.
Analysis results       and support loads contained herein reflect the layout arrangement       shown on marked isometric C-381-350, Sheet 1, Revision C. Any significant     modifications to the layout of this system of piping and or
'y truly yours, W.A.Massie/dj Attachment F.Noon, Manager Eastern Region WNI Support M.P.Li 1 ley~+ATE-gO-5 cc: R.E.Smith-'lL, 1A R.C.McCredy, RGE-1L, M.P.Lilley, t<GE-1L, lA T.R.Hei s, RGE<-1L B.H.Bell, GA?-'1 L', lA P.N.Cameron, GAI-1L, lA B.A.Snow, RGE-1L J.C.Hutton, RGB,-, 1L, lA\'}}
                                          'y its restraints will warrant reanalysis           of this piping system.
Minor design changes or construe.ion modifications will generally not affect stress results 'and suppor t recottrtendations.           However, case by case review of the discrepancies can be used to determine overall system behavior and effects.
If any   questions     exist relative to the     abo've transmittal, please contact W. A. Massie     of Westinghouse.
truly yours, F. Noon, Manager Eastern Region   WNI     Support W. A. Massie/dj Attachment
 
M. P. Li 1 ley                             ~
                                              +ATE-gO-5 cc: R. E. Smith - 'lL, 1A R. C. McCredy, RGE - 1L, M. P. Lilley, t<GE - 1L, lA T. R. Hei s, RGE<- 1L B. H. Bell, GA? -'1 L', lA P. N. Cameron, GAI - 1L, lA B. A. Snow, RGE - 1L J. C. Hutton, RGB,  
                                  , 1L, lA
                                      \
                        '}}

Latest revision as of 20:53, 29 October 2019

Forwards Re Ginna Nuclear Power Plant,Seismic Upgrading Program Piping Stress Analysis,Main Steam Sys,Section 200. Minor Design Changes or Const Mods Will Generally Not Affect Stress Results & Support Recommendations
ML17250A587
Person / Time
Site: Ginna Constellation icon.png
Issue date: 07/18/1980
From: Noon F
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Lilley M
ROCHESTER GAS & ELECTRIC CORP.
Shared Package
ML17250A588 List:
References
RGE-80-95, ST-SST-108, NUDOCS 8009170298
Download: ML17250A587 (3)


Text

I IIestinghoose Nater Reactor Nuclear Technology Oivision Electric Corporation Divisions Box 355 Pittsburgh Pennsylvania 15230 July 18, 1980 ST-SST- 108 RGE 95 Mr. M. P. Li lley

. Rochester Gas 8 Electric J9 East Avenue Rochester, Hew York 14649

Dear Mr. Li lley:

ROBERT EMMETT GINHA NUCLEAR GENERATING STATION R, E. Ginna Seismic Upgrading Program Main Steam Stress Re ort Transmitted herein is the piping stress report for the'R. E. Ginna Nuclear Generating Station Unit No. 1 Main Steam System, Section 200, SDTAR-80-05-'08..

Analysis results and support loads contained herein reflect the layout arrangement shown on marked isometric C-381-350, Sheet 1, Revision C. Any significant modifications to the layout of this system of piping and or

'y its restraints will warrant reanalysis of this piping system.

Minor design changes or construe.ion modifications will generally not affect stress results 'and suppor t recottrtendations. However, case by case review of the discrepancies can be used to determine overall system behavior and effects.

If any questions exist relative to the abo've transmittal, please contact W. A. Massie of Westinghouse.

truly yours, F. Noon, Manager Eastern Region WNI Support W. A. Massie/dj Attachment

M. P. Li 1 ley ~

+ATE-gO-5 cc: R. E. Smith - 'lL, 1A R. C. McCredy, RGE - 1L, M. P. Lilley, t<GE - 1L, lA T. R. Hei s, RGE<- 1L B. H. Bell, GA? -'1 L', lA P. N. Cameron, GAI - 1L, lA B. A. Snow, RGE - 1L J. C. Hutton, RGB,

, 1L, lA

\

'