ML19276G795
| ML19276G795 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 07/05/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19276G793 | List: |
| References | |
| NUDOCS 7908270515 | |
| Download: ML19276G795 (1) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION y ' g( 3 g 5
,-f;E WASHINGTON, D. C. 20555 k *.O 8
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE SEISMIC REANALYSIS OF REACTOR COOLANT PIPING COMMONWEALTH EDIS0N COMPANY ZION STATION UNITS NOS. 1 AND 2 DOCKET NOS. 50-295 AND 50-304 In response to IE Bulletin 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.
Westinghouse 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.
r The updated WESTDYN code used in the reanalysis of the primary cochmt 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 the reanalysis of the reactor coolant piping system has been performed 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 7908270616
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