ML19242A092
| ML19242A092 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/02/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Clayton F ALABAMA POWER CO. |
| References | |
| NUDOCS 7907310223 | |
| Download: ML19242A092 (2) | |
Text
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UNITED STATES l'
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M In Reply Refer To:
RII:JPO 50-348 50-364 Alabama Power Company Attn:
F. L. Claytca, Jr.
Executive Vice President Post Office Box 2641 Birmingham, Alabama 35291 Gentlemen:
The enclosed Bulletin 79-14 is forwarded to you for action. Written responsea are required.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
]D#n g-A James P. O'Reilly t
Director
Enclosure:
1.
IE Eulletin No. 79-14 2.
Listing of IE Bulletins Issued In Last Twelve Months J i.- l ruw 7907310223
JUL 2 1979 Alabama Power Company cc w/ encl:
A. R. Barton Executive Vice President Post Office Box 2641 Birmingham, Alabama 35291 J. T. Young Vice President-Production Post Office Box 2641 Birmingham, Alabama 35291 C. Biddinger, Jr.
Manager-Corporate Quality Assurance Post Office Box 2641 Bi rmingham, Alabama 35291 H. O. Thrash Manager-Nuclear Generation Post Office Box 2641 Birmingham, Alabama 35291 H. G. Hairston, III Plant Manager Drawer 470 Ashford, Alabama 36312 R. E. Hollands, Jr.
QA Supervisor Post Office Box U Ashford, Alabama 36312
UNI 17.D 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 nonconservative results.
One issue involved algebraic sumation of loads in some seismic analyses.
This was addressed in show cause orders for Beaver Valley, Fitzpatrick, Maine Yankee and Surry.
It was also addressed in IE Bulletin 79-07 which waa 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 systees revealed a number of nonconfomances to design documents which could potentially affect the validity of seismic analyses.
Nonconformances are identified in Appendix A to this bulletin.
Because apparently significant non-conforsances to design documents have occurred in a number of plants, this issue is generic.
The staf f has detemined, where design specifications and drawings are used to obtain input info m tion for seismic analysis of safety-related piping systems, that it is essential for these documents to reflect as-built con-figurations.
'=here 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 b-taken by Licensees and Permit Holders:
All power reactor facility licensees and construction permit holders are requested to verify, unless verified to an equivalent degree within the last 12 months, that the seismic analysis applies to the actual configura-tion of safetyrelated piping systems.
The safety related piping includes Seismic Category I systems as defined by Regulatory Guide 1.29, " Seismic Design Classification" Revision 1, dated August 1, 1973 or as defined in the applicable FSAR.
For older plant
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y ments did not exist at the time of li 1 DUPLICATE DOCUMENT actual configuration of these safety-ments.
Entire document previously entered into system under:
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