ML20052A099
| ML20052A099 | |
| Person / Time | |
|---|---|
| Site: | 07105507 |
| Issue date: | 03/26/1982 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Ross D ENERGY, DEPT. OF |
| References | |
| RTR-REGGD-07.004, RTR-REGGD-07.006, RTR-REGGD-07.008, RTR-REGGD-7.004, RTR-REGGD-7.006, RTR-REGGD-7.008 NUDOCS 8204270089 | |
| Download: ML20052A099 (2) | |
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U.S. Department of Energy B
ATTH: Dr. Donald H. Ross A
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MS-E-201 Washington, DC 20545 Gentlemen:
This refers to your letter dated April 26, 1978 requesting our review of the ORHL HFIR Spent-Fuel-Element shipping package.
In connection with our review, we need the information identified in the enclosure to this letter.
Picase advise us within thirty (30) days from the date of this letter when this infonnation will be provided.
Sincerely, Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, PMSS cc: DOE, Oak Ridge Operations Office ATTH: Mr. William II. Travis P.O. Box E Oak Ridge TN 37830 Distribution: w/ enc 1 Docket File d NRC PDR IEHQ(3)
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NRC FORM 318 (10-80) NRCM 0240 OFFICIAt_ RECORD COPY
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Additional Inf:rmation for the HFIR Spent Fuel Element Shipping Cask (Docket No. 71-5507)
Enc 1 to ltr dtd: 'Y.AR 2 61982 STRUCTURAL 1.
Justify the adequacy of the model tests to demonstrate the energy absorbtion capability of the packaging. Consider material properties and geometry.
Identify criteria for dimensions and material properties; compare the established criteria with the scale models to demonstrate the adequacy of the models.
2.
Provide a structural analysis of the cask to show that it meets the requirements of 10 CFR Part 71 for nomal conditions of transport and hypothetical accident conditions. The load combinations of Regulatory Guide 7.8, and the stress limits of Regulatory Guide 7.6 may be used for the containment vessel.
3.
Show that the containment vessel closure boli:s are adequate to absorb the total energy of the containment lid and weight of the contents for a top end 30-foot drop. Assess the effects of permanent defomation, if any, on the containment system.
THERMAL The DOE Certificate of Compliance specifies a maximum heat load of 3.75 kw per package; this is more than the 3.57 kw reported as analyzed in the SARP (ORNL/ENG/1M-12, November 1977). Show that the higher heat load requested satisfies all the requirements of 10 CFR Part 71.
CONTAIMENT Establish a containment acceptance criteria for normal conditions of transport and accident damage conditions. Regulatory Guide 7.4 may be used to establish this criteria.
OPERATING PROCEDURES, TESTING AND MAINTENANCE Specify a containment testing program. The containment test criteria should be based on the established containment criteria for notwal conditions of transport and accident damage conditions. The schedule of testing should be developed to assure continued safe performance of the package in use. Regulatory Guide 7.4 may be used for initial testing and for periodic testing of each package. For assembly verification, it is recommended that a test of sufficient sensitivity to limit the maximum release to a type A quantity ig 10 dags is used, however, a leak test sensitivity greater than 1x1 The minimum gensitivity of 1x10~9 at-gm / scc, would not be required.
at-cm /sec, (air at 1 atm and 25'C leaking to a 10- at ambient) as specified in ANSI N14.5 should be met.
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