ML20198J780
| ML20198J780 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/23/1986 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| GN-925, NUDOCS 8606030210 | |
| Download: ML20198J780 (2) | |
Text
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Geo' gs Power Company e_-j 9 r
' Flouta 2, Box 299A 9'
Waynesboro, Georgis 30830 Telephone 404 554 9961
- 404 724-8114 Southern Company Services. Inc.
Post Office Box 2625 -
Birmingham, Alabama 35202 s
Telephone 205 870-6011 May.23, 1986 Director of Nuclear Reactor Regulation File:. X7BC35 Attention:' Mr.
B.' J. Youngblood Log:
GN-925 PWR Project. Directorate #4 Division of PWR Licensing A
, U. S.. Nuclear -Regulatory Commission Washington, D.C.
20555 GN-874, CONWAY TO DENTON, 4/16/86 REF:
NRC DOCKET NUMBERS 50-424 AND 50-425
- CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 CODE ADDENDA 0F RECORD FOR PIPING STRESS ANALYSIS
Dear Mr. Denton:
- As a result of a telephone conversation held with your staff on Friday, May.23, 1986, we are providing'the following clarification to the referenced letter. This letter requested the use of subarticle NC-3600 of the Winter 1981 Addenda to the 1980 Edition of the ASME Section III Code for class 2 piping stress analysis and subarticle ND-3600 of the Summer 1984 Addenda ~to the 1983 Edition of the ASME Section III Code for 3 piping stress analysis.
GPC engineering and codes personnel have reviewed the, changes provided by the later Addenda, and have concluded that the proposed itequirements would not impact or alter the materials used in -the analysis or'* the fabrication of piping systems. Therefore, the statement in our referenced letter with respect to "not less restrictive" was intended to mean that the material requirements shall continue to meet the ASME Section III, 1974 Edition with Summer 1975 Addenda requirements.
In addition, the use of these later Code Addendas shall be referenced in our FSAR Section 3.9.B.1.4.2 " Seismic
. Category 1 Itens Other Than NSSS" and 3.9.B.2 " Dynamic Testing and Analysis."
These two sections of the FSAR reflect the Code of Record as being ASME B&PV 1974 edition with Summer 1975 Addenda (see reference 1 in FSAR pages 3.9.B.1-6
!and 3.9.B.2-7).
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3, Director of Nuclear Reactor Regulation File:
X7BC35-May 23, 1986 LOG:
GN-925 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 R. A. Thomas J. E. Joiner, Esquire B. W. Churchill M. A. Miller (2)
B.-Jones (Esquire)
G. Bockhold, Jr.
NRC Resident Inspector D. C. Teper W. C. Ramsey L. T. Gucwa Vogtle Project File 0502V i
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