ML20212C377
| ML20212C377 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/22/1986 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| 0943V, 943V, GN-1254, NUDOCS 8612300184 | |
| Download: ML20212C377 (2) | |
Text
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Georgo Pbwer Company Post Offico Box 282 T'
Wayresborc, Georgia 30830 4
Telephone 404 554-9961 404 724-8114 Southem Corepany Sent.ces,Inc.
Pbst Office Box 2625 Birmingham, Alabama 35202 Telephone 205 8704011 December 22, 1986 g
i n
Dir-ctor of Nuclear Reactor Regulation File: X7BC35 Atte'qtion:
Mr. B. J. Youngblood Log GN-1254 PWR Project Directorate #4 Division of PWR Licensing A
". S. Nuclear Regulatory Commission Washington, D.C.
20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUC110N PERMIT NUMBERS CPPR-108 AND CPPE-109 VOCTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 COMPUTER PROGRAM VALIDATION
Dear Mr. Denton:
In recent telephone conversations, your staff has requested additional information on the. verification of the BASEPLATE and FAPPS computer programs listed in subsection 3.9.B.1 of the Vogtle FSAR. The validation information is discussed below and will be included in the next FSAR amendment.
The BASEPIATE code was verified by comparing test problem results with the results of. CDC BASEPLATE II code runs for the same problems. The code capabilities investigated include:
(1)' Calculation of maximum bolt pullout, bolt SRSS shear force, and bolt
. safety factor (2) Maximum principal stress of plates (3) Weld shear stresses (4) Pressure on concrete In each case the results of the BASEPLATE code were consistent with the CDC
. benchmark.
'The FAPPS code was verified by comparing test problem results with the results of STRUDL code runs for the same problems. The code capabilities compared include stiffness matrix formulation and stress calculation techniques common to both codes. In other applications where FAPPS calculations are not within STRUDL capabilities, hand calculations were performed to ensure proper operation of the code.
In each case, the FAPPS results were consistent with the STRUDL results or the hand calculations.
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8612300184 861222
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.PDR ADOCK 05000424 A
PDR.
m Director of Nuclear Reactor Regulation December 22, 1986 Page 2 If your staff requires any additional information, please do not hesitate to contact me.
Sincerely, J. A. Bailey Project Licensing Manager JAB /sm xc:
R. E. Conway NRC Regional Administrator R. A. Thomas NRC Resident Inspector J. E. Joiner, Esquire D. Feig B. k. Churchill, Esquire R. W. McManus M. A. Miller (2)
L. T. Cucwa B. Jones, Esquire Vogtle Project File G. Bockhold, Jr.
0943V i
a l
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