ML20198B359
| ML20198B359 | |
| Person / Time | |
|---|---|
| Site: | 07109103 |
| Issue date: | 10/28/1985 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Clay Johnson NAC INTERNATIONAL INC. (FORMERLY NUCLEAR ASSURANCE |
| References | |
| NUDOCS 8511060463 | |
| Download: ML20198B359 (2) | |
Text
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Q l-4fo3 RETURN T3 A Ala:Idia FCTC: RHO 00'88 71-9103 00T 2 8 Y Nuclear Assurance Corporation ATT!!: Mr. C. R. Johnson 57 Peachtree Parkway fiorcross, GA 30092 Gentleren:
This refers to your application dated July 18, 1985, reouesting an amendnent to the t'odel No. NLI-6502 package.
In connection with our review, we need the infomation identified in the enclosure to this letter.
Please advise us within 30 days from the date of this letter when this infomation will be provided. The additional infomation requested by this letter should be submitted in the fom of revised pages.
If you have any questions regarding this ratter, we would be pleased to reet with you and your staff.
Sincerely.
Origin-1 "igned br (BRMCAS3. R CDOMAID Charles E. l'acDonald, Chief Transportation Certification Branch Division of Fuel Cycle and ffaterial Safety, f: MSS
Enclosure:
As stated Distribution: w/ encl RH0degaarden (2)
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N;;C FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY
Nuclear Assurance Corporation Model No. N1.I-6502 Packaoe Docket No. 71-9103 OCT 2 8 W Enc 1 to ltr-dtd:
DRAUINGS Provide (or reference if previously provided) engineering drawings of the fuel basket, fuel cans, etc.
CRITICALITY 1.
The figure of the Model No. NLI-6502 Cask Basket !!odel shown on page 4 of the application has inconsistencies with KEN 0 input for cavity cross-sectional area. The KENO input includes a central cavity area of 12 inches by 12 inches which was used in calculations; the figure on page 4 exceeds these dimensions. Please resolve this discrepancy.
2.
The shield region design drawings of the cask indicate a depleted uranium region surrounding the steel liner of the cavity. The lead shield can then be taken as the second reflector region following the depleted uranium. The most reactive single unit KEN 0 calculation should be rerun with the uranium as the close reflector.
3.
An error exists in the KEHO problems in the application of the axial (3) boundry condition (b.c.).
Since the reflection b.c. is specified at the end of the 3-inch (7.62 cms) steel region, an effective gap of 6 inches in the Boral sheet is used in the calculation.
Although this is conservative, it is negated by the non-conservative b.c. placed at the end of 23.25 inches of the Boral sheet. This' doubles the length of the Boral in the calculation and is non-conservative. All KENO calculations should be rerun with the correct gap and Boral length. Also, the assuned water gaps used in the calculations should be justified.
4.
The atomic number density of B-10 in the Boral region should be reduced by at least 25% to account for clumping and inhonogenities.
This new concentration of B-10 should be used in the KENO reruns requested by Items 2 and 3 above.
In addition, the applicant should supply a copy of the Boral manufacturer's specification sheet for B C-Al density and thickness, Al clad thickness, and areal B-10 Eton concentrations for the 1/8-inch thick Boral sheets.
OPEPATIHG PROCEDllRES Provide detailed loading and unloading protedures for the revised contents.
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OFFICIAL RECORD COPY