ML20212H663
| ML20212H663 | |
| Person / Time | |
|---|---|
| Issue date: | 03/03/1987 |
| From: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Haelsig R NUCLEAR PACKAGING, INC. |
| References | |
| REF-PROJ-M-44 NUDOCS 8703060183 | |
| Download: ML20212H663 (2) | |
Text
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.rientlemen, We have examined the NuPac Internal Report " Impact Performance and Testing of the NuPac CP-9" submitted by letter dated December 17, 1986, in support of the proposed NuPac CP-9 Scale Model Test Program. This document and two others also submitted are material in support of your topical report (TR) for the CP-9 concrete cask' design. From discussions during our meeting of December 17, 1986, this report is to be an appendix to the TR to be. submitted. The CP-9 Scale Model Test Program which is to be developed,-is also to be submitted in conjunction with and as a part of the TR.
We have concluded that we see nothing incorrect in your understanding of scale model testing. Clearly, however, we do not have sufficient information to judge whether your test program and TR will be adequate. At such time as you have fully developed the CP-9 Scale Model Test Program in conjunction with the TR, we would expect to review these prior to any actual testing of a CP-9 cask scale model.
We also want'to take this opportunity to make a few coments regarding your submitted report and your proposed test program. Hopefully, these will be helpful to you in addressing issues concerning our prospective review of the test program and TR.
-e The report appears to reflect an appropriate understanding of scale model design and test design suited to experiments with sub-scale reinforced concrete structures.
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e The report, however, provides insufficient information on the actual i
prototype and model designs, concrete design, and potential handling i
scenarios to be replicated by test (i.e., elements of your test program) to support concurrence in the approach.
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The role (s) and relationship of the model testing to your analytical model or code should be explained. Also, explain these with respect to your design analysis, design verification, and/or validation of proof against accidental impact.
In conclusion, the objectives of the test
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program are not yet clear and must be carefully developed.
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The report does not address the thermal environment, with the exception of describing potential use of a deliberately weak concrete. The analysis of thermal effects on the potential structural response and design suitability of the actual cask will be closely examined in the topical report.
It should be noted that the NRC requires a high degree of proof prior to accepting designs exceeding the limits of the appropriate codes, regulations, and standards (such as ACI 349-75).
The potential thermal environment and temperature produced metamor-phosis which may occur with your design may require such proof of design suitability.
e Be aware that additional potentially critical impact events may be postulated on the basis of the actual design and proposed usage scenarios, when developed, e
The acceptance criteria indicated should reflect both comprehensive review of potential failure modes corresponding to the hypothesized accident, and adequate measurement and/or tests to verify meeting the criteria.
Original signed by Jolm F. Roberts John P. Roberts Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety Distribution:
ME3ebTW.43 File, PDR TCAF File'
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DATE:03/J?/87
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