ML20247R465
| ML20247R465 | |
| Person / Time | |
|---|---|
| Issue date: | 04/04/1989 |
| From: | Steve Ruffin NRC |
| To: | NRC |
| References | |
| REF-PROJ-M-42 NUDOCS 8904070319 | |
| Download: ML20247R465 (3) | |
Text
_ _ - _ - _ _ _ _
. - n so
-[
'o,, UNITED STATES
/ o- NUCLEAR REGULATORY COMMISSION
( ;$ WASHINGTON, D. C. 20555
$\,..../ APR 0 41989 Pr0 ject M-42 NOTE TO FILE
SUBJECT:
COMMENTS SENT TO TRANSNUCLEAR, INC., FROM LAWRENCE LIVERMORE NATIONAL LABORATORY The enclosed comments on TN Letter E-10795 dated March 16, 1989, were received by computer on March 28, 1989. These comments were sent to Transnuclear, 'Inc. , from Lawrence Livermore National Laboratory, af ter NRC Project Manager approval.
Stevie R. Ruffin
Enclosure:
i As stated '
OPS I\
8904070319 890404 PDR PROJ PDC M-42
o .
a W R 0 4 1989 Project M-42 NOTE TO FILE
SUBJECT:
COMMENTS SENT TO TRANSNUCLEAR, INC., FROM LAWRENCE LIVERMORE NATIONAL LABORATORY The enclosed comments on TN Letter E-10795 dated March 16, 1989, were received by computer on March 28, 1989. These comments were sent to Transnuclear, Inc. , from Lawrence Livermore National Laboratory, after NRC Project Manager approval. g. g .
Stevie R. Ruffin
Enclosure:
As stated Distribution:
Project M-42 POR NRC File Center JPRoberts SRuffin FBrown 0FC :IMIF :IMIF : : : : :
_I_r._____ . _hbS..[____..__.[_________[.._______[_________[.________
DATE:bl@f/89 / :I#/I?'/89 - - -
' 0FFICIAL RECORD COPY l
. ',', Cuaued.s on 'IN Intter E-10795 Dated March 16, 1989 D.tring review of the 'IN-24 TSAR, concern has developed about potential buckling of the fuel bundle basket inside the cask. 'Ihis concern is reflected in the analysis of two accidents: a side drop of the' cask frun a height of 18 inches, and a cask tip-over accident. Questions about these accidents are presented below.
j A. 'Ihe 18-Inch Side Drop
- 1. Provide calculations for the mass and stiffness of the single-degree of firedom system. Show the calculation for the maxinnan deceleration load of 83 g.
- 2. In the analysis to find the equivalent beam width of the frame model, what load was used and which stress component was campared between the panel model and the frame model, and at what location?
In the frame model analysis, is there any plastic deformation observed and at what locations? Please note that the interaction formula in the ASME Cbde applies only to linear elastic analyses.
- 3. In our opinion, Equation 6a of the ASME Code Subsection NF-3322.1 (1986 Edition) should be used in calculating the allowable compressive stress Wmtm the formula in Apperrilx F is for material with a clear yield point such as carbon steel. A reduction in the factor of safety or increase in the allowable stress can be used to convert level A to Invel D service conditions. Allowable stress of 1.5 times that of Equation 6a is jtdged appropriate for Invel D service conditions. Please evaluate the new design using this criteria.
- 4. Provide comparison of impact analysis results for several basket orientations (such as 0, 15, 30, and 45 degrees) to demonstrate that the worst basket orientation is 0-degrees.
B. 'Ihe Tip-Over Accident Based on submitted information on 18-inch side drop on an unyielding surface without impact limiters, we concluded that an impact limiter is essential for the tip-over accident. Please provide information on the impact limiter. 'Ihe information cheuld include a description of the impact limiters, their material piventies, their force-deformation curves, the method of calculating the force-deformation curves, and amnnntions made. Please also provide information on tip-over analysis. 'Ihe analysis information should include the description of the method of analysis, n = =ptions made, validity of the l ammntions, analysis results, and acceptance criteria.
I 1
3