ML20235K238
| ML20235K238 | |
| Person / Time | |
|---|---|
| Issue date: | 07/14/1987 |
| From: | Odegaarden R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 8707160217 | |
| Download: ML20235K238 (2) | |
Text
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MEMORANDUM FOR:
The File FROM:
Richard H. Odegaarden, SGTB, NMSS j
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SUBJECT:
NAVAL REACTORS - DIG CASK J
t Attendees DOE-NR NRC Matt Petitclair C. R. Chappell
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H. W. Lee R. H. Odegaarden Introduction A meeting was held at the request of Naval Reactors (NR) at Silver Spring, Maryland, on June 23, 1907, concerning NR's response to an letter dated l
January 29, 1987, which pertained to the Model No. D1G Cask.
J Discussion Naval Reactors indicated that the package (if considered alone, without the skid) may not meet the acceptance standards for shielding following the normal condition one-foot drop test. Also, the closure bolts could possibly yield.
However, Naval Reactors believes the package would meet the acceptance standards if the container shipping craddle is included in the free drop evaluation to provide some cushion for the container. Since the shipping craddle and the container will be tied together as an unit transport, the staff has no objection to this approach. Naval Reactors agreed to revise the Safety Analysis Report to show that the package meets the 1-foot drop test in the orientation that the container is normally transported.
Naval Reactors stated that container leaktightness is not needed following the accident condition because of limited dispersive radioactive material in the contents. Therefore, the closure bolts could exceed their yield stress, l
provided the bolts do not stretch beyond their ultimate strain. The staff l
reiterated our objection to the use of ultimate stress as the design limit for l
closure head bolts. Also, it does not appear that the closure bolts could absorb the kinetic energy of the closure plates and contents without failing l
under 30-foot drop test conditions. Navat Reactors agreed to reexamine and to revise their bolt analysis and to strengtnen the closure head design, if necessary. This could likely be done by welding.
B707160217 B7071 A PDR ORG EUSDOE PDR
Naval Reactors agreed to describe and justify of the operational controls that will be used to assure the lowest service temperature to which the container will be subjected during transportation is sufficiently high to preclude brittle fracture failure of the containment vessel.
@l Elped by '
Richard H. Odegaarden, Project Manager Transportation Branch Division of Safeguards and Transportation, NMSS DISTRIBUTION:
Meeting Attendees l
NMSS r/f SGTB r/f CEMacDonald
- NRC PDRE Docket File Meeting Notebook
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- SGTB 4
NAME:RH0degarden:kd:CRb'pell:
DATE:7/07 /87
- 7//7/87 0FFICIAL RECORD COPY
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