ML19242A093
| ML19242A093 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/02/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stewart W FLORIDA POWER CORP. |
| References | |
| NUDOCS 7907310227 | |
| Download: ML19242A093 (1) | |
Text
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Jul 2 1979 In Reply Refer To:
RII:JPO 50-302 Florida Power Corporation ATTN:
W. P. Stewart, Manager Nuclear Operations P, O. Box 14042, Mail Stop C-4 St. Petersburg, FL 33733 Gentlemen:
The enclosed Bulletin 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,
'Q j D,2 y-A James P, O'Reilly t
Director
Enclosure:
1.
IE Eulletin No. 79-14 2.
Listing of IE Bulletins Issued In Last Twelve Months 4./
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7310227
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- Florida, Power Corporation cc w/ encl:
G. P. Beatty, Jr.
Nuclear Plant Superintendent Post Office Box 1228 Crystal River, Florida 32629 4,
400e i 42
l'NITED STATES NUCLEAR REGULATORY COMMISSION k'ASHINGTON,
D.C.
20555 July 2, 1979 IE Bulletin No. 79-14 SEISMIC ANALYSES FOR AS-BUILT SAFETY-RELATED PIPING SYSTEMS Desertption 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 summation 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 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.
Nonconfermances are identified in Appendix A to this bulletin.
Because apparently significant non-conformances to design documents have occurred in a number of plants, this issue is generic.
The staf f has determined, 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.
klere 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 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 plants, where Seismic Category I require-ments did not exist at the time of lier
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actual configuration of these safety-ri DUPLICATE DO UMENT ments.
Entire document previously entered into system under:
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