ML20054L400
| ML20054L400 | |
| Person / Time | |
|---|---|
| Site: | 07105787 |
| Issue date: | 06/29/1982 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20054L399 | List: |
| References | |
| NUDOCS 8207080069 | |
| Download: ML20054L400 (4) | |
Text
Foyn NRC618 U.S. NUCLE AR REGULATORY COMMISSION U
p *
- M CFR 71 CERTIFICATE OF COMPLIANCE For Radioactive Mttricts Pichges 1,(2) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d ) Pages No. 1.(e) Total No. Pages 5787 0
USA /5787/B( )F 1
2
- 2. PRE AMBLE 2.(a)
This certificate is issued to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The p.ickaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10, Code of Federal Regulations, Part 71, " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions."
2.(c)
This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.
- 3. Tnis certificate is issued on the basis of a safety analysis report of the package design or application-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
Oak Ridge National Laboratory Safety Analysis Report for Packaging (SARP) of the Post Office Box X Oak Ridge National Laboratory Shipping Cask D-38 Oak Ridge, TN 37830 Report ORNL-5406, Rev. 1, August 7, 1981.
3.tc)
Docket No.
71-5787 4.
CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
- 5. Osscription of Packaging and Authorized Contents Model Number, Fissile Class, Other Conditions, and
References:
(a)
Packaging (1) Model No.:
D-38 (2) Description Packaging for fissile and large quantities of radioactive material contained in special form encapsulation.
Plutonium is doubly contained.
The inner cavity of the cask is a 300 Series Stainless Steel Schedule 40 pipe with inside dimensions 6-1/16 in. diameter x 13-13/16 ir.. high.
The outer shell is a 300 Series Stainless Steel Schedule 30 pipe 20-1/2 in high.
Shielding consists of depleted uranium metal with a thickness of 2-3/4 in.
The top opening plug is held in place by eighteen 1/2-in. studs equipped with nuts.
l The plug is sealed with a neoprene gasket. The cask is mounted on a 14-in.
square x 5/8-in. thick base plate.
Six of the studs are extra long so that i
a protective shroud may be used during transport.
The cask is bolted with l
four 1-in. bolts to a 3-ft. square pallet. The package gross weight is 1525 pounds.
l
~(3)
Drawings The cask is constructed in accordance with Union Carbide Corporation, l
Nuclear Division, Oak Ridge National Laboratory Drawing Nos. M-12133-CD-126E l
Rev.12 and M-12166-CD-022 Rev.1.
l l
l l
8207080069 820629 i
Page 2 - Certificate No. 5787 - Revis* ion No. 0 - Docket No. 71-5787 5.
(b) Contents (1) Type and form of material (i) Solid radioactive material including U-235 encapsulated to meet the requirements of special form material defined in 10 CFR 571.4(o).
(ii) Solid radioactive material including U-233 and Pu-239 encapsulated to meet the requirements of special form material defined in 10 CFR 571.4(o); plutonium bearing solid must have a second special form encapsulation.
(2) Maximum quantity of material per package The maximum internal heat not to exceed 80 watts; (i)
For the material described in 5(b)(1)(i) the mass of U-235 not to exceed 500g.
(ii) For the material described in 5(b)(1)(ii) the mass of U-233 or Pu-239 not to exceed 3509 (iii) For any combination of the materials described in 5(b)(1)(i) and 5(b)(1)(ii) the total combined mass of U-235, U-233, and Pu-239 not to exceed 350.
9 (c) Fissile Class I
l 6.
Special form capsule may be held within DOT Specification 2R containers within the cask cavity.
7.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
8.
Expiration date:
July 31, 1987.
REFERE'NCE Oak Ridge National Laboratory Report No. ORNL-5406, Rev.1, August 7,1981.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION hw Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS DateduN 2 9 1992
V.
S U.S. Nuclear Regulatory Commission Transportation certification Branch Approval Record Model No. D-38 Packaging Docket No. 71-5787 The DOE has requested NRC approval for the Model No. D-38 shipping package by letter dated August 24, 1981. The staff has reviewed the request and supporting documentation. On the basis of the review of information provided in Report No. ORNL-5406, Rev.1, August 7,1981, the staff concludes that the package design satisfies the applicable requirements of 10 CFR Part 71.
Compliance with 10 CFR 571.31 (General Standards for all Packaging) has been adequately demonstrated by analysis. The demonstration of compliance with 10 CFR 571.35 (Standards for Normal Conditions of Transport for a Single Package) has also been done by analysis.
The analysis has been reviewed and found adequate.
Compliance with 10 CFR 571.36 (Standards for Hypothetical Accident Conditions for a Single Package) has been do'ne by analysis and has been found to be generally adequate by the staff.
The staff has considered the effect of the high value for specific energy of steel in compression assumed in the applicant's analysis.
Assuming a high specific energy results in conservatively high forces on contents, closures, etc.;
however, it results in underestimates of package deformation. An independent calculation has been performed by the staff for the 30-foot free drop test. The independent evaluation indicates that there would be no reduction in packaging effectiveness.
Primary containment for the package is provided by special form capsules.
The requirements of 10 CFR 571.42 are satisfied by doubly encapsulating plutonium in special form capsules.
In addition to the primary containment provided by the special form capsules secondary containment is provided by the sealed cask and the sealed DOT Specification 2R container which may be used. The secondary containment (not required) is not maintained following the 10 CFR Part 71, Appendix B test sequence due to loss of the seals under the fire test environment.
Shielding is provided by uranium encased in steel.
It has been shown that the cask shielding effectiveness is not significantly reduced as a result of normal and accident condition tests of 10 CFR Part 71; therefore, satisfying DOT requirements for normal conditions assures satisfication of 10 CFR Part 71 requirements for accident conditions.
V.
An infinite number of damaged and undamaged packages containing the requested contents have been shown by KEN 0 calculations to be subcritical, satisfying Fissile Class I requirements.
The single package is subcritical due to mass limits of fissile material under the most reactive conditions of 10 CFR Part 71.
Q {k Af
==
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date: JUN 2 01997 9
l l
l r
I l
l