ML20235W641
| ML20235W641 | |
| Person / Time | |
|---|---|
| Site: | 07109019 |
| Issue date: | 09/29/1987 |
| From: | Winslow T GENERAL ELECTRIC CO. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20235W644 | List: |
| References | |
| 28625, NUDOCS 8710160341 | |
| Download: ML20235W641 (5) | |
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' }RETURS TU 393-58GENERALhELECTRIC
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. NUCLEAR FUEL & COMPONENTS MANUFACTURING GENERAL ELECTRIC COMPANY e P.O. BOX 780 a WILMINGTON, NORTH CAROUNA 28402 September 29, 1987 fdb 4
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9 Mr. Charles E. JacDonald, Chief
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TransportationkCertification Branch
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Division of Fpel Cycle & Material Safety 00cKET CLERK L'SEP301337* x U. S. Nuclear 4pRegulatory Commission
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Dear Mr. ' MacDondd :
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Subject:
NRC Certificate of Compliance USA /9019/AF
References:
- 2) Supplement, TP Winslow to C9 MacDonald, 2/7/86
- 7) Letter, TP Winslow to CE'MacDonald, 3/24/87 On February 24, 1987 the NRC requested additional information in support of GE-Wilmington's application dated 1/6/86, as supplemented 2/7 and 12/22/86.
The application was prepared to
. demonstrate that the BU-7 package meets current requirements of 10 CFR 71 and, therefore, 'should be - identified - as complying with the
" Safety Series No. 6, IAEA Safety Standards Regulations for the Safe Transport of Radioactive Materials, 1973 Re' vised Edition ( As Amended)".
In the 12/22/86 submittal, a consolidated Application, Revision 1, was provided to f acilitate NRC review.. Responses to your questions are in the form of pages that can easily 'be inserted into the application and are submitted as follows:
NRC Inquiry 1)
" Drawing Note 6 does not provide an acceptable method for marking the package.
The selection of a method to mark the package must consider the ef fects of the fire accident and the need to be able to identify the package af ter a fire accident.
10 CFR S71.85( c) requires that the packaging be durably marked."
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i GENERAL h ELECTRIC l
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MacDonald September 29, 1987 Page 2 GE Response: - GE Licensing Drawing Number 112D1592, Revision 6,
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should be inserted in Appendix A of the 12/22/86 su bm it t al.
This drawing has been changed to show the following:
1
( a)
A 1/16" thick stainless steel identification plate (drawing location C-4).
(b)
A clarification to the 1/8 inch thick silicone rubber gasket to identify the actual MIL specification to which the gaskets are to be purchased.
These are the specifications that applied to the gaskets used in the performance testing (drawing location B-6).
'( c)
Note #5 has been changed to call out stainless steel as material for the blind rivets.
(d)
Note #6 has been further clarified by adding the appropriate regulatory reference 10 CFR 71.85(c).
Al so, in note #6, the information to be placed on the plate has been expanded to i
include "Wilming ton, N.C., US A" for easier owner identification.
NRC Inquiry 2)
" S tr uc tural" "Specify the density of the insulating media used in j
the prototype testing program."
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GE Response:
The calculated density of the fire retardant foam (SP-9) us ed in the BU-7 container (Serial No. K-1878), subj ected to the hypothetical accident condition tests conducted in April, 1980 is 8.35 pounds per cubic foot.
This value is consistent with the j
present drawing callouts of 7 to 9 pounds per cubic foot on BU-7 q
licensing drawing 112D1592.
NRC Incuiry 3)
" Operating procedures should be presented sequentially
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in the actual order of performance and such items as j
inspections prior to loading, cautionary notes on package handling, limits on package contents, torque 3
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GENER AL $ ELECTRIC Y
C.
E.
MacDonald September 29, 1987 Page 3 requirements on closure bolts and the closure ring l
bolt, installation of a security seal, and L
instructions pertinent to receiving and unloading the package (10 CFR 571.89) should be addressed.
The section on acceptance testing should discuss the l
l tests and inspections that will be performed prior to i
first use of the packaging (10 CFR 571.85).
State the acceptance criteria for each test and inspection and the action to be taken if noncompliance is encountered.
Provide a general description of the leak test procedure, e.g.,
test type, package configuration, system internal pressure, observation time, acceptance criteria.
The maintenance program should describe the actions taken to ensure continued performance of the packaging.
The program should include periodic testing, inspection, and replacement sched ules, as well as criteria for replacement and repair of components and subsystems on an as-needed basis."
GE Response are page changes (identified as Revision 2, dated
?/29/87) and should be inserted in section 5.0 of the 12/22/86 submittal replacing pages 15, 16, and 17 currently identified as Rev ision 1.
Once NRC approval has been obtained, a separate request referencing this submittal will be made to the Department of -
Transportation since it will be the IAEA Competent Authority Certification that will approve this package to 1973 IAEA requirements.
General Electric personnel would be pleased to discuss this matter with you and your staf f as you may deem necessary.
Very truly yours, GE NUCLEAR ENERGY
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T.
P.
Winslow, Manager Licensing & Nuclear Materials Management
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TPW/RHDF/sbm Attachments
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GENERAL h ELECTRIC
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i ATTACHMENT 1 GE LICENSING DRAWING NUMBER 112D1592, REVISION 6 MM
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