ML20135F819

Forwards Request for Addl Info Re 850710 Application for Approval of Model CE-250-2.Addl Info Should Be Submitted in Form of New Application.Schedule for Submitting Info Due within 30 Days of Ltr Date

ML20135F819
Person / Time
Site:	07109022
Issue date:	09/13/1985
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Gerrald L SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
References
NUDOCS 8509170422
Download: ML20135F819 (3)

Text

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• h , 7/McM RETURN TO A Machim FCTC: RHO 39g g 71-9022 gp 13 g Exxon Nuclear Company, Inc.

ATTH: Mr. L. D. Gerrald P.O. Box 130 Richland, WA 99352 Gentlemen:

This refers to your application dated July 10,1985, requesting approval of the Model f!o. CE-250-2 package as meeting current 10 CFR Part 71 requirements.

In connection with our review, we need the information identified in the enclosure to this letter.

Please advise us within 30 days fron the date of this letter when this information will be provided. The additional information requested by this letter should be submitted in the forn of a new application. If you have any questions regarding this matter, we would be pleased to meet with you and your staff.

Sincerely.

0"I !n91 E Signed by

%S E. u,1m Charles E. HacDonald, Chief Transportation Cert',fication Branch Division of Fuel Cycle and

. flaterial Safety,imSS t

Enclosure:

As stated Distribution: w/ enc 1 RH0degaarden (2)

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l NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY ,, __ _

Exxon fluclear Company, Inc.

t'odel flo. CE-250-2 Package Docket No. 71-9022 3

Encl to ltr dtd:

STRUCTURAL

1. The application needs to consider the revised pressure requirenents (e.g., nomal condition's reduced external pressure and increased external pressure and hypothetical accident condition's innersion for all packages) in 10 CFR Part 71.

2. The evaluation of the subject package to meet both the 4-foot drop test and the 30-foot drop test of 10 CFR part 71 is based solely on comparisons to three sinilar packages on which two were full-scale drop tested. Af ter an examination of the three sinilar packages, the staff found that, except for the untested Westinghouse Model

?!o. BB-250-2 shipping package, the two full-scale tested packages were both lighter than the subject package. In the case of the 30-foot CG over the seal ring bolt drop, the gross weight of a package may nake a difference as to whether or not the lid of the outer container will remain intact and thus prevent the release of the contents. As for the Westinghouse Model No. BB-250-2 shipping package, it weights about the sane as the subject package. Ilowever, the closure of the outer container of the Westinghouse package is stronger than the subject package. Instead of using a standard DOT Specification 17)!,12-gauge closure ring with 5/C-inch bolt and nut, the Westinghouse package is bolted with six,1/2-inch bolts around the top of the drun body. Thus, extrapolation of certain 30-foot drop test for the subject package is not valid, since the three sinilar packages are either stronger or lighter than the t'odel No. CE-250-2 package.

The application should evaluate the perfornance of the seal ring bolt for the 30-foot drop test. The consequences of bolt damage for a drop onto the bolt with CG directly above it nust be considered in terns of any reduction in package effectiveness. Furthemore, the danage due to secondary inpact resulting from an oblique angle drop should also be evaluated.

3. part 71 requires the safety analysis report to address the cumulative effects of the hypothetical accident conditions. Thus, tne application should address the effect of puncture inpact onto the seal ring bolt after the subject package has been through the 30-foot CG over the seal ring bolt drop.

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ama THERMAL Provide a thernal analysis or test results denonstrating the closure of the inner container 's not compromised by the thernal accident test.

The test results comparing the Model flo. CE-250-2 package to the tiodel flo. Pu 10-I package is vague and not well documented.

CRITICALITY Provide a criticality safety analysis for the single package in accordance with 10 CFR 671.55(b).

OPERATIf!G PROCEDURES The operating procedures should provide sufficient discussion (outline of procedural steps) to demonstrate compliance with Subpart G to 10 CFR Part 71.

ACCEPTANCE TESTS The section on Acceptance Testing should be nore specific as to what inspections will be perforned, acceptance criteria, and action taken if nonconpliance is encountered.

MAINTENANCE PROGRAM The raintenance progran should specifically address the inspections, reolacenent schedule, and procedures for such itens as gaskets, fasteners, and verniculite.

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NRC FORM 318 (10 80) NRCM O240 OFFICIAL RECORD COW