ML14184A081
| ML14184A081 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 05/22/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14184A080 | List: |
| References | |
| SER-790522, NUDOCS 7907130174 | |
| Download: ML14184A081 (1) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE SEISMIC REANALYSIS OF REACTOR COOLANT PIPING CAROLINA POWER AND LIGHT COMPANY H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 In response to IE Bulletin 79-07, Carolina Power and Light Company identified 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 reanalyzed 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 H. B. Robinson Unit 2 Final Safety Analysis Report.
The updated WESTDYN 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 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:
MAY 2 2 1979 7907130 1-