ML20215A237
| ML20215A237 | |
| Person / Time | |
|---|---|
| Site: | 07100420 |
| Issue date: | 06/10/1987 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20215A223 | List: |
| References | |
| NUDOCS 8706160570 | |
| Download: ML20215A237 (1) | |
Text
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U.S. NUCLEAR REsULATORY COMMISSION 1. APPROVAL NUMBER nac roaa sit 0 ll
+n> QUALITY ASSURANCE PROGRAM APPROVAL g ,,0,#fon S suMsER g FOR RADIOACTIVE MATERIAL PACKAGES 3 j l ,I I ,
l Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974. as amended, and Title 10. Code of Federal l Regulations. Chapter 1. Part 71. and in reliance on statements and representations heretofore made in item S by the person named in llem l)l
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l l 2. the Quality Assurance Program edentified in item S is hereby approved. This approval is issued to satisfy the requirements of section lg I l 71.101 of 10 CFR Part 71. This approvalis subject to allapplicable rules. regulations and orders of the Nuclear Regulatory Commission lg )
l- now or hereafter in effect and to any conditions specified below.
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I 7 NAME 3 EyFIRATION DATE II I Radiation Technology, Inc. April 30, 1991 I l
g STREET ADDRESS I Lake Denmark Road 4 DOCKET NUMBER 'g I CITY STATE ZIP CODE '
1 Rockaway NJ 07866 71-0420 lll
- 5. QUALITY ASSURANCE PROGRAM APPLICATION DATE(S) I l April 30, 1987 g 6. CONDITIONS j l i I
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! Activities authorized by this approval: procurement, maintenance, repair, l and use to be executed with regard to transportation packages in special l i
I form. All other activities (i.e., design, fabrication, assembly, testing, i I and modification) shall be satisfied by obtaining certifications from l l package suppliers that these activities were conducted in accordance with I i an NRC-approved QA program. It shall remain the responsibility of the I i licensee-user that all transportation activities meet the requirements of I 10 CFR 971.101.
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l PDR ADOCK 07100420 l C PDR I
i l MR THE U.S. NUCLEAR REGULATORY COMMISSION I i /ar es E.J' Mac onald
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l CHIEF. TRANSPORTATION CERTIFICATION BRANCH DATE
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l DIVislON OF FUEL CYCLE AND MATERIAL SAFETY g l OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS l
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- % UNITED STATES
,p f,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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Departtrent of Transportation GOSLAR Package USA /0093/8(M)F Encl to ltr dtd: M 10 W STRUCTURAL
- 1. Provide a physical description of the i scale model and relate it to the full scale package (drawings or tabular table).
i j 2. Describe the tests performed on the scale model and provide a description of the impact surface.
- 3. Describe the damage to the scale model, including the fuel basket.
- 4. Provide detailed engineering drawings of the cask lid and closure region. Demonstrate the assumption used in the safety analysis report that the lid bolts are only stressed in compression during the accident test sequence.
THERMAL The effect of convection on lead melt thickness should be addressed.
Convection in the melt region (liquid) could result in more melting due to higher heat transfer rates than that predicted by a pure conduction thermal model. (It may be necessary to reevaluate the shielding capabilities of the cask if convection effects indicate greater melting.)
CRITICALITY Provide additional details on the criticality model to show that the neutron reflector properties of the cask (steel-lead-steel) were taken into account.
Lead could result in 5 to 15% increases in keff values calculated with a water reflector. ,
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