ML19270H806
| ML19270H806 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/26/1979 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19270H804 | List: |
| References | |
| NCR-CEB-79-05, NCR-CEB-79-5, NUDOCS 8001030645 | |
| Download: ML19270H806 (1) | |
Text
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ENCLOSURE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 TENSILE ANCdOR CAPACITIES LOWER THAN ASSUMED IN DESIGN ALLOWABLES NCR CEB 79-5 10 CFR 50.55(e)
FINAL REPORT Description of Deficiency Progressive cracking of the heat affected zone of welded stud anchors in flexible plate connections has occurred in TVA general research and development program tests.
This results in lower tensile anchor capacities than assumed in establishing design allowables.
Safety Lnplications Statements Based on the results and conclusions of the testing program, a review of welded anchorages found the anchorages were adequate and would perform as designed under design loadings.
Therefore, had the deficiency gone uncorrected, it would not have adversely affected plant safety.
Corrective Action When this problem was discovered, a testing program was initiated to qualify the effect of plate flexibility on stud capabilities to withstand design loadings. The results of the tests are contained in CEB Report 79-18 (Attachment 1).
Based on the results of this report, guidelines were provided to evaluate and qualify the welded stud anchorages at Sequoyah Nuclear Plant (Attachment 2).
A review of anchorages in safety applications was conducted in accordance with these recommendations and guidelines. This review determined the anchorages were adequate.
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