ML19351D567
| ML19351D567 | |
| Person / Time | |
|---|---|
| Site: | 07106375 |
| Issue date: | 09/08/1980 |
| From: | James Corbett CHEM-NUCLEAR SYSTEMS, INC. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 17363, NUDOCS 8010100424 | |
| Download: ML19351D567 (1) | |
Text
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CHEM-NUCLEAR SYSTEMS INC. [.00 7/- (o 37 E o
P.O. Box 1866 e Bellevue, Washington 98009 e (206) 827 d> t l o3 9
DO'CKliEli 9
USNRC b
SEP 2 5 G80 > %
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E September 8, 1980 Matt TioFi
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Charles E. MacDonald, Chief' y '
1 Mr.
Transportation Branch 1-l N
Division of Certification, Fuel Cycle c;
i and Materials Safety, NMSS United States Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Docket No. 71-6375
References:
(1)
U.S. NRC Lettar, 6/23/80 (C of C Extension)
(2)
U.S. NRC Letter, 4/2/80 (Request for Info)
Dear Mr. MacDonald:
Your letter of June 23, 1980, reference (1), requests submittal of additional renewal application information by September 30, 19 80, sixty days prior to the November 30, 1980 expiration of the Certificate of Compliance.
In response to this request, we are submitting the enclosed summary of modifications to the package and its associated Safety Analysis Report.
A completely revised Safety Analysis Report, incorporating all listed modifications, will be submitted to you prior to expiration of the Certificate of Compliance.
The enclosed summary of modifications will bring this package to existing standards, as recommended by current USNRC Regulatory Guide criteria.
These changes assure a safe, reliable package for transport of Type "B" materials.
In addition, the changes will permit us to respond to your request for information, reference (2), in a format, defined in USNRC Reg. Guide 7 9.
This format should greatly simplify your review of theg uignificant package improvements.
Sincerely, CHEM-1;UCLEAR SYSTEMS, INC.
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J.
Stewart Corbett
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Manager, Licensing & Safety
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SUMMARY
OF MODIFICATIONS TO MODEL CNS 4-45 (PB-1) 1.
SAR MODIP'ICATIONS Revisions to the Safety Analysis Report will include; a.
An altered contents description deleting irradiated fuel elements or assemblies.
b.
An expansion of scope and detail of existing evaluations consistent with current Regulatory Guide criteria for content and format.
Supplementary evaluations asseesing the c.
1 integrity of redesigned package features consistent with current Regulatory Guide criteria.
i d.
Revision or replacement of the drawings to j
indicate materials of construction for all components.
2.
PACKAGE MODIFICATIONS j
Significant package redesign features include:
a.
Complete replacement of energy absorbing end buffers with overpack type energy absorbers providing protection to the package for impacts at all orientations.
b.
Replacement of existing pressure relief valves and pressure gauges with flush mounted ASME type drain and vent ports, c.
Relocation and redesign of trunnions to allow
-installation of overpacks.
d.
Redesign of lids and closure flanges to provide increased strength and greatly improved sealing capabilities.
l '
.