ML19242A108
| ML19242A108 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Vogtle  |
| Issue date: | 07/02/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | John Miller GEORGIA POWER CO. |
| References | |
| NUDOCS 7907310254 | |
| Download: ML19242A108 (2) | |
Text
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UNITED STATES
,o, NUCLE AR REGULATORY COMMISSION 2
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101 MARIE TT A ST., N W. SUITE 3100 AT L ANT A. G E ORGI A 30303
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N In Reply Refer To:
RII:JPO 50-321 50-0-424 50-4 Georgia Power Company ATTN:
J. E. Miller, Jr.
Executive Vice President 270 Peachtree Street Atlanta, GA 30303 Gentlemen:
The enclosed F,ulletin 79-14 is f orwarded to you for action. Written responses are required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, Yny-A James P. O'Reilly t
Director
Enclosure:
1.
Listing of IE Bulletins Issued In Last Twelve Months Y90 7310253 462 229
JUL 2 1979
. Georgia Power Company cc w/ encl:
M. Manry, Plant Manager Post Office Box 442 Baxley, Georgia 31513 C. E. Belflower Site QA Supervisor Post Office Box 442 Baxley, Georgia 31513 K. M. Gillespie Ccastruction Project Manager Post Office Box 282 Waynesboro, Georgia 30330 E. D. Groover QA Site Supervisor Post Office Box 282 Waynesboro, Georgia 30830
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C.
20555 July 2, 1979 IE Bulletin No. 79-14 SEISMIC ANALYSES FOR AS-BUILT SAFETY-RELATED PIPING SYSTEMS Description of Circumstances:
Recently two issues were identified which can cause seismic analysis of safety-related piping systems to yield conconservat've results.
One issue involved algebraic sumation of loads in some seismic analyses.
This was addressed in s'aow cause orders for Beaver Valley, Fitzpatrick, Maine Yankee and Surry.
It was also addressed in IE Bulletin 79-07 which was sent to all power reactor licensees.
The other issue involves the accuracy of the information input for seismic analyses.
In this regard, several potentially unconservative factors were discovered and subsequently addressed in IE Bulletin 79-02 (pipe supports) and 79-04 (valve weights). During resolution of these concerns, inspection by IE and by licensees of the as-built configuration of several piping systems revealed a number of nonconformances to design documents which could potentially affect the validity of seismic analyses.
Nonconformances are identified in Appendix A to this bulletin.
Because epparently significant non-conformances to design documents have occurred in a number of plants, this issue is generic.
The staf f has detennined, where design specifications and drawings are used to obtain input information for seismic analysis of safety-related piping systems, that it is essential for these documents to reflect as-built con-figurations. Where subsequent use, damage or modifications af fect the con-dition or configuration of safety-related piping systems as described in documents from which seismic analysis input information was obtained, the licensee must consider the need to re-evaluate the seismic analyses to con-sider the as-built configuration.
Action to be taken by Licensees and Permit Holders:
All power reactor facility licensees and construction permit holders are reqtested to verify, unless verified to an equivalent degcee within the last 12 months, that the seismic analysis applies to the actual configura-tion of safetyrelated piping systems.c ~"
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Seismic Category I systems as defined i
Design Classification" Revision 1, da jDUPLICATEDOCUMENT the applicable FSAR.
For older plant
,' Entire document previously entered ments did not exist at the time of li actual configuration of these safety, into system under:
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