ML19309B414
| ML19309B414 | |
| Person / Time | |
|---|---|
| Site: | 07109010 |
| Issue date: | 03/26/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19309B411 | List: |
| References | |
| NUDOCS 8004040124 | |
| Download: ML19309B414 (6) | |
Text
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Form NRC418 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICAT'E OF COMPLIANCE 10 C R 71 For Radioactive Materials Packages 1.(e) To7i No. Pages PackT/9010/8 F.
1.(d) Pages No.
Identificati n 1.( ) Certificate Number 1.(b) Revision No.
1.(c)
US 1
9010 6
- 2. PREAMBLE 2.tal This certificate is issued to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the Department of Transportation Hazardo:;s 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 packaging and contents desaibed in item 5 below, meets the safety standards set forth in Subport C of Titte 10. Code of Federal Regulations. Part 71, ** Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions."
2.(c)
This artificate does not relieve the mnsignor from cornpiiance with any recuirement of the regulations of the U.S. Department of Transportation or other spoticable regulatory agencies, including the government of any country through or into which the package will be transported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or applicatiort-3.(a)
Propered by (Narne and address):
3.Ib)
Title end identification of report or application:
NL Industries, Inc.
NL Industries, Inc. application dated Nuclear Division March 7, 1980.
l P.O. Box 2046 3,(c)
Docket No.
7],qg]g U41minntnn nr lQAQQ
. 4. CONDITION 5 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. Description of Packaging and Authorized Contents, Model Number, Fissde Class, Other Conditions, avuf
References:
(a) Packaging
'(1 ) Model No.: NLI-1/2 (2)
Description A depleted uranium, water, and lead shielded shipping cask, encased in stainless steel, and equipped with balsa impact limiters.
The cylindrical cask body is 195-1/4 inches long by 47-1/8 inches OD. The principal shielding consists of 2-3/4 inches of depleted uranium, 2-1/8 inches of lead, and 5 inches of water.
A 7/8-inch thick stainless steel outer'shell is welded to a solid stainless steel forging at each end of the cask.
The outer shell of the cask is sur-rounded by a 1/4-inch thick steel water jacket that is also attached to the end l
forgings. A water expansion tank is welded to the water jacket shell. The innter cask cavity is formed by a 1/2-inch thick, stainless steel cylindrical shell; welded at its top end to the upper cask forging and at its bottom end to l
a circular plate.
l There are two separate configurations of the cask.
Configuration (A): The containment vessel is a right Circular stainless steel shell,12-5/8 inches ID by 178 inches inside langth by 1/4-inch thick, located within the inner cask cavity. The containmt a vessel is closed and sealed by a 5-inch thick, composite steel and uranium closure' head, twelve,1-inch diameter bolts, and a silver plated, metallic 0-ring.
Eight of the twelve closure bolts 8004.040)
Page 2 - Certificate No. 9010 - Revision No. 6 - Docket No. 71-9010 5.
(a) Packaging (continued)
(2) Description (continued) are used to secure the containment vessel to the upper cask forging.
Closure of the cask cavity is by a 1-1/2-inch thick ste':1 closure head, eight,1-inch diameter bolts, and elastomer 0-ring.. Ti.e radioactive contents are positioned and supported within the containment vessel (inner container) by an aluminum basket and internal support structure.
Configuration (B): The containment vessel is the 1/2-inch thick inner cavity shell. The 1/4-inch thick inner container is not used. The cask cavity is closed by two closure heads.
The inner head is a 6-inch thick, composite steel and uranium plate secured to the upper cask forging by twelve,1-inch diameter bolts and sealed with a silver plated, metallic 0-ring. The outer head is 1-1/2-inch thick steel plate secured to the top of the upper cask forging by eight,1-inch diameter bolts and sealed with an elastomer 0-ring. The radioactive contents are positioned and supported within the containment vessel (inner cask cavity) by a modified aluminum basket and internal support structure.
The package, including impact limiters, has an overall length of 237 inches and an outside diameter o' 75 inches. The maximum weight of the contents is 1,600 pounds. The weignt of the package is approximately 47,500 pounds.
(3) Drawings The Model No. NLI-1/2 shipping cask is constructed in accordance with the following Nationa'l Lead Company Drawing Nos.:
Gene'ral 70514F, Sheet 1, Rev. 7, Cask and Trailer General Arrangement 70514F, Sheet 2, Rev. 8, Cask and Trailer General Arrangement 70d85F, Sheet 1, Rev. 2, Spent Fuei Cask Details i
70885F., Sheet 2, Rev. 2, Spent Fuel Cask Details 70885F, Sheet 3, Rev.1, Spent Fuel Cask Details 70885F, Sheet 4, Rev. 1, Spent Fuel' Cask Details 70887F, Sheet 1, Rev.1, Outer Closure Head Configuration (A) l l
70516F, Sheet 1, Rev. 8, Spent Fuel Cask General Assembly 70562F, Sheet 1, Rev. 8, Inner Container 70562F, Sheet 2,13ev.4,InnerContainer Configuration (B) 70888F, Sheet 1, Rev. 2, Spent Fuel Cask General Assembly 70886F, Sheet 1, Rev. 2, Basket' Concept 70884F, Sheet 1, Rev. 2, Inner Closure Head -
Page 3 - Certificate No. 9010 - Revision No. 6 - Docket No. 71-9010 (b) Contents (1) Type and form of material (i)
Irradiated PWR or BWR uranium oxide fuel assemblies of the following specifications:
PWR BWR Fuel form Clad UO2 pellets Clad UO2 pellets Cladding material Zr or SS Zr or SS Maximum initial fuel pin pressure at 100*F, psig 550 200 Maximum initial U content / assembly, kg 475
' 97 Maximum average initial U-235 enrichment, w/o 3.70 2.65 Maximum bundle cross section, inches 8.75 5.75 Fuel pin array size 14x14/15x15 7x7 16x16/17x17 8x8 Maximum active fuel length, inches 144 144 Maximum specific power, kw/kgU 40 27 Maximum burnup, MWD /MTU 40,000 34,000 Minimum cooling time, days 150 120 The PWR type assemb.ies may be shipped either with or without burnable poison rods or control rods.
,ek l
1
Page 4 - Certificate No. 9010 - Revision No. 6 - Docket No. 71-9010 5.
(b) Contents (continued)
(1) Type and form of material (continued)
(ii) Solid, non-fissile, irradiated hardware and neutron source components.
(iii) Byproduct and special nuclear material in the form of irradiated uranium and plutonium oxide fuel rods.
Prior to irradiation, the maximum enrichment in U-235 plus plutonium not to exceed 3.70 w/o.
(2) Maximum Quantity of material per package The maximum decay heat load per package not to exceed 10.6 kilowatts, and; (1)
Item 5(b)(1)(1) above, one (1) PWR fuel assembly or two (2) BWR fuel assemblies.
Above assemblies to be contained in their respective fuel baskets as shown on National Lead Company Drawing No. 70562F, Sheet 1, Rev. 8 or 70886F, Sheet 1, Rev. 2.
(ii)
Item 5(b)(1)(ii) above, weight not to exceed 1,600 pounds.
(iii) Item 5(b)(1)(iii) above, the maximum mass of U-235 plus plutonium shall not exceed 4.0 kg. Fuel rods shall be contained in fuel baskets as shown on National Lead Compa y Drawing No. 70562F, Sheet 1, Rev. 8 or 70886F, Sheet 1, Rev. 2.
(c) Fissile Class III Maximum number of packages per shipment One (1) 6.
The cask cavity and containment vessel (inner container) shall be dry (no free water) when delivered to a carrier for transport. Residual moisture shall be removed from tne cask cavity and containment vessel by the methods described in Section XV of the Application. Removal of residual moisture from cask cavity when package is used in Configuration (B) is not required providing the decay heat load does not exceed 2 KW.
The containment vessel shall be filled with 1 ATM of helium.
7.
Prior to each shipment, the package shall meet the tests and criteria specified in Section XVI of the Application.
i
j Page 5 - Certificate No. 9010 - Revision No. 6 - Docket No. 71-9010 d.
The helium coolant is considered part of the package contents. The radioactive limits specified in 171.35(a)(4) do not apply.
9.
The package contents shall be so limited that under normal conditions of transport, the sum of the gamma and neutron dose rates shall not exceed 21 mrem /hr when measured at a distance of three (3) feet from the exterior surface of the package.
The neutron shielding) tank shall be filled with a mixture of water and ethy l
10.
glycol (52% by volume.
- 11. The structures used to support the package on the transport vehicle shall be as described in the Application.
- 12. Any system used for cooling down the package shall be provided with a pressure relief device set so that during the cool-down process, the maximum pressure in the contain.
ment vessel cannot exceed 310 psig when the package is used in Configuration (A) or 365 psig when the package is used in Configuration (B).
- 13. The systems and components of each packaging shall meet the periodic tests and criteria specified in Section XVI of the Application.
14.
Repair and maintenance : hall be as described in Section XVI of the Application.
- 15. As needed, appropriate component spacers shall be used in the cask cavity to limit movement of contents during shipment.
16.
Prior to.first use.each packaging shall meet the acceptance tests and criteria specified in Sections XIII and XIV of the Application when used in Configuration (A) and in Appendix A to Sections XIII and XLV when used in Configuration (B).
- 17. The package authorized by this certificate is hereby approved for use under the general licen'se provisions of 10 CFR 571.12(b).
g 18.
Expiration date: March 31,1985.
l REFERENCE NL Industries, Inc. application dated March 7,1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. Ma' Donald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date: MAR 2 61980
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