ML19296A041
| ML19296A041 | |
| Person / Time | |
|---|---|
| Site: | 07109122 |
| Issue date: | 10/18/1978 |
| From: | Kinkade K CHEM-NUCLEAR SYSTEMS, INC. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| KHK-048, KHK-48, NUDOCS 7810300104 | |
| Download: ML19296A041 (11) | |
Text
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KHK 048 c.
CHEM-NUCLEAR SYSTEMS INC.
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Q'Y' P.O. Box 1866 4 Bellevue,hhington 98009 e (206) 827-0711
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,1 October 18, 1978 Y
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Mr. Charles E. MacDonald, Chief Ca l l g Transportation Branch l
Division of Fuel Cycle and Material Safety f
U.S. Nuclear Regulatory Commission Washington D.C. 20555 I
Reference:
NRC Letter to CNSI dated 10/11/78.
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Subject:
Application for Certificate of Compliance for CNSI Cask 18-450 f
(Big Bertha), NRC Docket No. 71-9122.
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Centlemen:
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Pursuant to the requirements of Section 71.21 of 10 CFR 71, we are submit-ting our application requesting authorization to deliver LSA Radioactive Material containing greater than Type A quantities of radioactive material to a carrier for transport in the CNSI Model No.18-450 Cask.
The drawing has been revised to reflect the solid horizontal I-Beams through-out the structure, with the vertical outside stringers modified to allow the horizontal I-Beams to pass through. Also, a short analysis is included for the top portion of the vertical stringers.
Please replace Sheet 1, Rev. F of Drawing 182-201 with 182-201, Rev. G, Sheet 1.
The drawings have been revised to reflect the above change to the I-Beam.
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,Page Two KHK 048 Application for Certificate of Compliance for CNSI Cask 18-450 (Big Bertha), NRC Docket No. 71-9122.
Your immediate attention in this matter is very much appreciated.
If you have any questions regarding this catter, I would be most happy I
to meet with you or talk with you at your convenience.
I Sincerely, CHEM-NUCLEAR SYSTDIS, INC.
5 Karl II. Kinkade Manager Engineering a
KHK/mm
Enclosures:
SAR Sheets 30, 31 & 32 - 2nd Addendum to Appendix D (8 each) y Table of Contents (8 each)
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Drawing 182-201, Rev. G, Sheet 1 of 1 (8 each) cc: Vince Stagliola, Boston Edison (w/o enclosures)
Ken Dufrane (w/o enclosures)
Bob Posik (w/o enclosures) z Tom McCord (w/o enclosures)
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a r n ;E3 TABLE OF CONTENTS ^
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- H 0.0 GENERAL INFORMATION 0-1 R-1 0.1 Introduction 0-1 0.2 Package Description 0-2 0.2.1 Packaging 0-2 0.2.1.1 General Description 0-2 0.2.1.2 Materials of Constructions, Dimensions & Fabricating Methods 0-2 0.2.1.3 Containment Vessel 0-3 0.2.1.4 Neutron Absorbers 0-3 0.2.1.5 Package Weight 0-3 0.2.1.6 Receptacles 0-3 0.2.1.7 Tiedown 0-3 0.2.1.8 Lifting Devices 0-4 0.2.1.9 Pressure Relief System 0-4 0.2.1.10 Heat Dissipation 0-4 0.2.1.11 Coolants 0-4 0.2.1.12 Protrusions 0-4 0.2.1.13 Shielding 0-4 0.2.2 Operational Features 0-5 0.2.3 Contents of Packaging 0-5 1.0 STRUCTURAL EVALUATION 1-1 e 1.
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Page 1.1 Structural Design 1-1 1.1.1 Discussion 1-1 1.1.2 Design Criteria 1-1 1.2 Weights and Center of Gravity 1-2 1.3 Mechanical Properties of Materials 1-2 1.4 General Standards for all Packages 1-2 1.4.1 Chemical and Galvanic Reactions 1-3 R-1,R-2 1.4.2 Positive Closure 1-3 R-1,R-2 1.4.3 Lifting Devices 1-3 1.4.3.1 Primary Lifting Lugs 1-3 R-1,R-2 1-4 R-1,R-2 R-3, R-4 1.5 Jot Applicable 1-5 p_1 - n_4 1.6 Normal Conditions of Transport 1-5 1.6.1 Heat 1-6 R-1,R-2 1.6.2 Cold 1-6 1.6.3 Pressure 1-6 R-1,R-2 1.6.4 Vibration 1-6a R-1, R-2 1.6.5 Water Spray 1-7 1.6.6 Free Drop 1-7 R-1,R-2 1.6.6.1 Flat End Drop l-7 R-1,R-2 1.6.6.2 Corner Drop 1-7 1.6.6.3 Side Drop 1-7 1.6.7 Corner Drop 1-8 1.6.8 Penetration 1-8 A.7 Hypothetical Accident Conditions 1-8 1.8 Special Form 1-8
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Page 1.9 Fuel Rods 1-8 2.0 THERMAL EVALUATION 2-1 R-1 2.1 Evaluation of Package Performance for Normal Conditions of Transport 2-1 2.2 Hypothetical Thermal Accident Evaluation 2-1 3.0 CONTAINMENT 3-1 3.1 Containment Boundary 3-1 3.1.1 Containment Vessel 3-1 3.1.2 Containment Penetration 3-1 3.1.3 Seals and Welds 3-1 3.1.4 Closure 3-1 R-1 3.2 Requirements for Normal Conditions of Transport 3-2 3.2.1 Release of Radioactive Material 3-2 R-1 3.2.2 Pressurization of Containment Vessel 3-2 3.2.3 Coolant Contamination 3-2 3.2.4 Coolant Loss 3-2 3.3 Containment Requirements for the Hypothetical Accident Conditions 4.0 SHIELDING EVALUATION 4-1 4.1 Discussion and Results 4-1
5.0 CRITICALITY EVALUATION
4-1 6.0 OPERATING PROCEDURES 6-1 6.1 Procedures for Loading the Package 6-1 6.2 Procedures for Unloading the Package 6-2
7.0 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM 7-1 7.1 Acceptance Tests 7-1 7.2 Maintenance Program 7-1 8.0 QUALITY ASSURANCE 8-1 9.0 Appendix A 9-1 R-1 10.0 Appendix B 10-1 R-2 11.0 Appendix C 11-1 R-1 12.0 Appendix D 12-1 R-3 12-2 R-1 12-3 R-1 12-4 12-5 12-6 12-7 12-8 12-9 12-10 12-11 12-12 12-13 12-14 12-15 12-16 12-17 12-18 12-19 12-20
Appendix D (continued) 12-21 12-22 12-23 12-24 12-25 12-26 12-27 12-28 12-29 Appendix D, Addendum II 12-30 12-31 12-32
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