ML20051Z576
| ML20051Z576 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 05/11/1982 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8205180184 | |
| Download: ML20051Z576 (2) | |
Text
't g.ygT,ENNM EE VALLEY AUTHORITY h l,,[db b e CNhTTANOOGA. TENNESSEE 37401 400 Chest;pyt Street Tower II AB'3
?,?.1.W \\3 May 11, 1982 BLRD-50-438/81-77 BLRD-50-439/81-76 U.S. Nuclear Regulatory Comission Region II ATDis James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Dear Mr. O'Reilly urIMOFFE NUCLFAR PIRif UNITS 1 Am 2 - ALwWABLE STRESSES POR PIPE SUPPORP DESIGN - BLRD-50-438 B1-77, BLRD-50-439/81 SEOND INPERIM REPORP
/
he subject deficiency was initially reported to NBC-OIE Inspector R. V. Crlenjak on December 7,1981 in accordance with 10 CFR 50.55(e) as NCR BIR CEB 8110. R is was followed by our first interim report dated December 30, 1981. Enclosed is our second interim report. We expect to subnit our next report by September 20, 1982.
If you have any questions concerning this matter, please get in touch with R. H. Shell at PTS 858-2688.
Very truly yours, TONESSEE VALLEY AITIHORITY L. M. Mills, Manager Nuclear Licensing Dnclosure cc Mr. Richard C. DeYoung, Director (Enclosure)
Office of Inspection and Enfor m nt U.S. Nuclear Regulatory Ccenitar.m Washington, DC 20555 l
I OFMCDL COPY.
J Is r/
8205160G4 r //<
An Equal Opportunity Employer
ENCIDSURE BFJmTNTE NUCLEAR PIJNr UNITS 1 AND 2 ALLOWABLE STRESSES FOR PIPE SUPIORT DESIGN 10 CFR 50.55(e)
NCR BLN CEB 8110 BLRD-50-438/81-77, BLRD-50-439/81-76 SECCND INTERIM REPORT Description of Deficiency For the upset condition for primary Joad sources, the Bellefonte FSAR indicates that allowable stresses for support designs is 1.0 times the normal condition AISC allowable stresses. W e procedures g ierning 3ellefonte Nuclear Plant piping analyses (Civil Engineering Branch Engineering Procedure CEB EP-21.12 and MA3 Analysis Handbook) indicate that a factor of 1.33 can be used. %is deficiency was caused by the EP and handbook beirs issued with the 1.33 factor in anticipation that the ASME Code would adopt the 1.33 factor.
We code adopted a factor of 1.0 instead of 1.33.
We factor of 1.33 was used in the design of pipe supports.
Interim Progress TVA is looking in depth at allowable stresses being used at all projects for all loading conditions to determine which factors should be used. Upon completion of this study, the Bellefonte FSAR and all analysis procedures will be made consistent and analyses will be reviewed to ensure cmpliance. TVA anticipates empletion of this study by September 1,1982.
l
-