ML19242A104
| ML19242A104 | |
| Person / Time | |
|---|---|
| Site: | Catawba, Perkins, Cherokee  |
| Issue date: | 07/02/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Dail L DUKE POWER CO. |
| References | |
| NUDOCS 7907310245 | |
| Download: ML19242A104 (2) | |
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UNITED sf Af tS
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NUCLEAR REGULATORY COMMISSION
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p attanta, osoncia 223 Jtjl. 2 1979 In Reply Refer Tot RIT:JPO 50-413. 50-414 50-488. 50-489 50-490. 50-491 50-492, 50-493,
Dake Power Company L. C. Dail Vice President Attat Design Engineering P. O. Box 31189 28242 Charlotte, North Carolina Centlement Written responses The enclosed Eullitin 79-14 is forwarded to you for action.
If you dov re additional information regarding this matter, please are required.
contact this office.
Sincerely,
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"Y As James P. O'Reilly Director
Enclosure:
1.
IE Eulletin No. 79-14 2.
Listing of IE Bulletins Issued In Last Twelve Months no c7
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90 7310245
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Duke Power Cocpany cc w/ enc 1:
D. G. Bess, Project Manager Post Office Box 223 29710 Clover. South Carolina J. 7. Moore, Project Manager Post offsee son 422 29340 Gaffney, South Carolina e
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UNITED STATES NUCLEAR REGULATORY COMMISSION VASHINGTON, 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 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.
Nonconformances are tdentified 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 staff has deteruined, 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 affect the con-dttion 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 f acility 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 Seissic Category I systems as defined by Regulatory Guide 1.29, " Seismic
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Design Classification" Revision 1, dated 5 _ MQ a r as defined in N-the applicable FSAR.
For older plants, w loup c-
'i ments did not exist at the time of licens j
,p actual conf tguration of these safety-rel:
Entire docnment jinto system under ments.
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