ML19256B459
| ML19256B459 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 05/25/1979 |
| From: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 7907110231 | |
| Download: ML19256B459 (2) | |
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iLLuumAriNo stoc.. Pume souant cLevitANo. OHIO 44101 m TELEPHON: (216) 6231350 m MAIL ADDRESS P O B0x 5000 Datwyn R Davidson v>CE P At s.DE NT Sv5TE M E NG:NE E CN3 AND CONSTRvCitON May 25, 1979 Mr. James G. Keppler, Director Region III Office of Inspection and Enforce =ent U. S. Nuclear Regulatory Co_ ission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
Perry Nuclear Power Plant IE Bulletin No. 79-07
Dear Mr. Keppler:
Ir accordance with your request, the following response is provided to IE Balletin 79-07 concerning seismic stress analysis of safety-related piping. The computer codes used in the seismic stress analysis of safety-related piping for the Ferry Nuclear Power Plant do not use algebraic su==ation of the codirectional spatial components or inter-=odal responses in the response spectrum analysis. Time history analysis was not used in seismic stress analysis of piping.
The piping co=puter programs used for the Ferry Nuclear Power Plant were checked against both benchmark problems and piping syste=s analyzed by other computer programs with acce; cable results.
Some exa=ples of these benchmark problems and acceptable programs used for verification are the follow'ng:
1 In tb + Balance of Plant area:
ASYE Sa=ple Proble= #1 in ASME publication " Pressure Vessel a.
and Piping 1972, Computer Programs Verification."
Frequency and mode shape comparisons to ANSYS, PIPESD and o.
Biggs example in his book " Introduction to Structural Dyna =ics."
835 206
.rES IS?g 790'2110;23/*
Mr. James G. Keppler May 25, 1979 Page 2 In the NSSS area the G.E. version of SAP (verified using Svanson 2.
System's ANSYS program) which is the parent progra=; is used for verification.
Since tne accuracy of the piping co=puter codes used for the Perry Nuclear that the concerns Power Plant have been verified by the above, we concludt of thir IE Bulletin are not applicable to the Perry Nuclear Power Plant.
Very truly yours, Dalwyn. Davidson Vice President System Engineering and Construction DRD/c V Mr. John G. Davis, Acting Director cc:
Office of Inspection and Enforcement U. S. Nuclear Regulatory C-ission Washington, D. C. 20555 836 207