ML19209B531
| ML19209B531 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point, Zion  |
| Issue date: | 07/05/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18136A035 | List: |
| References | |
| NUDOCS 7910100072 | |
| Download: ML19209B531 (1) | |
Text
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NUCLEAR REGULATORY COMMISSION 3 tg C) c.
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p SAFETY EVALUATION BY THE OFFICE OF lVCLEAR REACTOR REGULATION
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RELATED TO THE SEISMIC REANALYSIf 0F REACTOR COOLANT PIPING COMMONWEALTH EDIS_)N COMPANY ZION STATION UNITS NOS. 1 AND 2 DOCKET N05. 50-295 AND 50-304 In response to IE Sulletin 79-07, Commonwealth Edison Company identi-fied that the reactor coolant piping dynamic analysis performed by Westinghouse using the WESTDYN code in 1970 was performed using algebraic summation for intramodal responses. Westinchouse has rean-alyzed the reactor coolant system piping using an updated version of WESTDYN which combines intramodal responses by the absolute sum method.
The results of this reanalysis show only minor changes in the pipe stresses, support loads and equipment nozzle loads.
All stresses are within the allowable limits specified in the Zion Station Final Safety Analysis Report.
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The updated QESTDYN code used in the reanalysis of the primary coolant piping is contained in WCAP 8252, Revision 1, May 1977, " Documentation of Selected Westinghouse Structural Analysis Computer Codes". This code has been reviewed by the staff and is acceptable.
We find.hs reanalysis of the reactor coolant piping system has been performec: with an acceptable computer code and the results of the reanalysis meet the applicable requirements specified in the applicant's safety analysis report.
Date: July 5,1979 1131 349 9
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