ML20154B327
| ML20154B327 | |
| Person / Time | |
|---|---|
| Site: | 07105059 |
| Issue date: | 10/01/1998 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Maxin A NUCLEAR FUEL SERVICES, INC. |
| References | |
| NUDOCS 9810050166 | |
| Download: ML20154B327 (4) | |
Text
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Mr. Andrew M. Maxin October 1, 1998 j
Nuclear Fuel Services, Inc.
P.O. Box 337, MS 123 Erwin, TN 37650
Dear Mr. Maxin:
This refers to your application dated July 31,1996, requesting renewal of Certificate of Compliance No. 5059 for the Model No. NFS Uranyl Nitrate Tank Trailer package. Since an application was submitted at least 30 days before the expiration of the Certificate of I
Compliance, the Certificate of Compliance will not be deemed to have expired until final action on the application for renewal has been taken.
l In connection with our review, we need the information identified in the enclosure to this letter. As described in the enclosure to this letter, you should provide a Safety Analysis Report for the package, in accordance with the requiremente of Subpart D of 10 CFR Part 71.
Please advise us of the date by which you will provide the requested information. if you have any questions regarding this matter, we would be pleased to meet with you and your staff. Nancy Osgood is the project manager for our review of your application.
Ms. Osgood may be contacted at (301) 415-8513.
Sincerely, Original /s/ by:
Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Docket No.: 71-5059 1
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Enclosure:
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Distribution:
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"C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy
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l Encl. to Ltr. Dtd. October 1,1998 Docket No. 71-5059 i
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GENERAL l
l The Model No. NFS Uranyl Nitrate Tank Trailer package was originally approved by the Atomic Energy Commission in 1965. The first Safety Analysis Report (SAR) for the package was submitted to the Nuclear Regulatory Commission in 1981, and has not been updated since that time. The safety discussion in the SAR is partly based upon rules for I
Low Specific Activity radioactive material that have been superseded, and the discussion of package safety performance is partly based upon a Department of Transportation (DOT) tank trailer specification that is no longer included in DOT regulations. As a result of the foregoing, the safety basis for the package under normal and accident conditions is not clear.
We need an SAR for the package, which includes a package description in accordance with l
10 CFR 71.33 and a package evaluation in accordance with 10 CFR 71.35. The SAR l
should show that the design meets the requirements of Part 71, and clearly identify any provisions of the regulations which the design does not meet. Note that the information in NUREG-1609, " Standard Review Plan for Transportation Packages for Radioactive Material," may be helpful.
CONTENTS Specify the contents to be transported in the package, including the mass or activity limits for each radioactive isotope. Specify the chemical form and concentration of the trailer contents, and the limits within which they may vary. Provide the chemical and physical properties of the trailer contents (e.g., freezing temperature, solubility, saturation concentration, density, pH, etc.)
CRITICALITY Either show that the package would not release its contents under the Hypothetical Accident Condition test sequence specified in 10 CFR 71.73, or show that the contents would remain sub-critical if released (or partially released). The criticality evaluation should show there is adequate margin against criticality and should consider possible re-concentration or precipitation of the uranium contents after being released (e.g., reduced solubility, freezing, evaporation, chemical reaction with fire fighting agents or other chemicals, etc.).
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4 HYDROGEN GENERATION 1
Revise the application to include an assessment of the generation of hydrogen and other flammable gases in the package due to radiolysis. The assessment should show that the maximum hydrogen concentration in the gas space of the package does not exceed five j
5 percent by volume within a one year period.
i INTERNAL PRESSURE J
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The Safety Analysis Report (SAR) for the package should include an assessment of the I
Maximum Normal Operating Pressure (MNOP), as defined in 10 CFR 71.4. Any pressure i.
increase due to radiolytic generation of flammable and non-flammable gas should be included in the calculation of MNOP. The SAR should show that the tank is adequately designed for the combined effect of internal pressure and the pressure from liquid surge i.
under normal conditions of transport (e.g., surge due to the vibration test or the free drop j '
test).
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PACK. AGE TIE DOWNS
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The package evaluation should include a description of how the tank and any appurtenances are attached to the vehicle, and an evaluation of the tie down system in i
accordance with 10 CFR 71.45.
2 l-PACKAGE DESCRIPTION The package description in the Safety Analysis Report (SAR) for the package dated May 27,1981, references Department of Transportation (DOT) specifications that are not i
currently in ihe DOT regulations. Revise the application to include a description of the packaging. The SAR should include a detailed description of the containment vessel, including the containment boundary and a description of all containment system 4
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penetrations, containment system welds, drain or fill ports, valves, seals, vents, test ports, lids, cover plates, pressure relief devices, and other closure devices. Explicitly identify the containment boundary of the package. Include a description of the various appurtenances to the tank, including the overflow line, retaining pan, and spill tank, and clarify whether i
they are part of the containment t:oundary. Describe the structural features of the tank, such as the size, number, and location of the stiffening rings. Describe how the tank is fixed to the vehicle. Describe the operational features of the package, including operation of penetrations and pressure relief devices.
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. PACKAGING DRAWINGS The Safety Analysis Report dated May 27,1981, includes only sketches of the packaging.
The sketches do not show detailed features of the package that are pertinent to safety.
Revise the application to include engineering drawings of the packaging that show the general arrangement of packaging and contents, dimensions and tolerances of the packaging and contents, details of the package design and safety features, materials of construction, including material specifications as appropriate (e.g., ASME, ASTM, MIL),
material specification and thermal properties of the insulating materials, codes, standards, or other appropriate fabrication specifications, operational information (e.g., bolt torque, specifications of pressure relief devices), design details of containment system closures and penetrations, weld configuration and inspection methods for welds important to safety, maximum package weight, maximum weight and volume of contents, minimum volume of contents, and minimum void volume. Note that the information in NUREG/CR-5502,
" Engineering Drawings for 10 CFR Part 71 Package Approvals," may be helpful.
MAINTENANCE Revise the description of the periodic pressure test to clarify how the test is performed, and what components (or appurtenances) are tested. Revise the discussion of the test to clearly specify the acceptance criteria for the test.
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