ML19259C215
| ML19259C215 | |
| Person / Time | |
|---|---|
| Site: | Phipps Bend |
| Issue date: | 05/24/1979 |
| From: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 7906140406 | |
| Download: ML19259C215 (2) | |
Text
hl T\\
~
TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 500C Chestnut Street Tower II
~d
$C WAY Z 4 1979 3
-g 5
E5
-40 s
>y u:
ffo
'Pcc 4
Mr. James P. O'Reilly, Director m
Office of Inspection and Enforcement U.S. Nuclear Regulatory Cotmission Region II - Suite 3100 101 Marietta Street Atlanta, Georgia 30303
Dear Mr. O'Reilly:
'PHIPPS BEND NUCLEAR PLANT - REPORTABLE DEFICIENCY - TENSILE ANCHOR CAPACITIES LOWER TBAN ASSUMED IN DESIGN. ALLOWABLES (NCR CEB-79-17)
Initial report of the subject deficiency was made to Mike Gouge, NRC-OIE, Region II on May 7, 1979.
In compliance with paragraph 50.55(e) of 10 CFR Part 50, we are enclosing the first interim report of the subject deficiency. We anticipate sending the final report to you on or before August 17, 1979. If you have any questions concerning this matter, please call Tish Jenkins at PTS 854-2014.
Very truly yours, A
1
. E. C111 eland Assistant Manager 3f Power Enclo sure 2284 143
(
7 7 906140 V0f, ME-LAL COP)
An Eaual opportumty Emp8erw
ENCI45URE PHIPPS BEND NUCLEAR PLANT NCR CEB-79-17 REPORT NO. 1 (INTERIM)
TENSILE ANCHOR CAPACITIES LOVER THAN ASSUMED IN DESIGN ALLOWABLES 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.
Interim Progress TVA's testing of the stud anchors is still in progress. TVA expects to complete the testing program and analysis of results by August 1, 1979.
We anticipate that the final report will be transmitted to NRC on or before August 17, 1979.
2284 144 9
.