ML19263E945
| ML19263E945 | |
| Person / Time | |
|---|---|
| Site: | 07109010 |
| Issue date: | 05/25/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19263E944 | List: |
| References | |
| NUDOCS 7906290053 | |
| Download: ML19263E945 (1) | |
Text
.
Form NRC413 U.S. NUCLEAR REGULATORY CoMMISSloN U
CERTIFICATE OF COMPLIANCE gg C R 71 For Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) Pages No.
9010 5
USA /9010/B( )F I
1.(e) 7tal No. Pages
- 2. PREAMBLE 2.lal This certificate is issued to satisfy Sections 173.333a.173.394.173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Cepartment of Transportation Dangerous Cargoes Regulatines (46 CFR 146-149), as amended.
2.(b)
The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Titte 10. Code of Federal Regulations, Part 71, ** Packaging of Radioactive Materials for Transport and Transportation of Racioactive Material Under Cartain Conditions.**
2.fc)
This certificate does not relieve the consignor from compliance with any reouirement 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 transperted.
- 3. This certifieste is issued on the basis of a safety analysis report of the package design or applicatiort-i 3.fa) ~ Prepared by (Name and address):
3.!b)
Tide and identification of report or application:
NL Industries, Inc.
NL Industries, Inc. application dated
. Nuclear Division December 20, 1972, as supplemented.
P.O. Box 2046 l
Wilmington, DE 19899 3.le)
Docket No.
- 4. CoNOllioNS This certificate is corditional upon the fulfilling of the tv:uirements of Subpart D of 10 CFM 71, as applicable, tad the conditions specified in item 5 below.
1
- 5. Description of Packaging and Aumorized Contents, Model Nurnoer, Fissile C! ass, Cther Conditions, and
References:
1 (a) Packaging (1) Model No.: NLI-1/2 l
(2) ' Description N
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 surrounded by' a 1/4-inch thick steel water jacket that is also attached to the end 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 a circular plate.
2303 351 O
7 906 29 0 073 C
Page 2 - Certificate No. 9010 - Revision No. 5 - Docket No. 71-9010 5.
(a) Packaging (continued)
(2) Description (continued)
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 length by 1/4-inch thick, located within the inner cask cavity. The containment 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 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 steel closure head, eight 1-inch diameter bolts, and elastomer 0-ring. The radioactive contents are positioned and supported within the containment vessel (inner container) by an alumir.um 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 con-tainer 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 of 75 inches. The maximum weight of the contents is 1600 pounds. The weight of the package is approximately 47,500 pounds.
2,303 352
- +5
~
Page 3 - Certificate No. 9010 - Revision No. 5 - Docket No. 71-9010 5.
(a) Packaging (continued)
(3) Drawings The Model No. NLI-1/2 shipping cask is constructed in accordance with the following National Lead Company Drawings Nos.:
General 70514F, Sheet 1, Rev. 6, Cask and Trailer General Arrangement 70514F, Sheet 2, Rev. 7, Cask and Trailer General Arrangement l'
70885F, Sheet 1, Rev. 1, Sr int Fuel Cask Details 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)
{
i 70516F, Sheet 1, Rev. 8, Spent Fuel Cask General Assembly 70562F, Sheet 1, Rev. 8, Inner Container 70562F, Sheet 2, Rev. 4, Inner Container Configuration (B) 70888F, Sheet 1, Rev. 2, Spent Fuel Cask General Assembly 70886F, Sheet 1, Rev. 2, Basket Concept l
70884F, Sheet 1, Rev. 2, Inner Closure Head I
(:,) Contents l
.<- w n (1) Type and form of material (i)
Irradiated PWR or BWR uranium oxide fuel assemblies of the following specifications:
2303 353
Page 4 - Certificate No. 9010 - Revision Nc. 5 - Docket No. 71-9010 5.
(b) Contents (continued)
(1) Type and form of material (continued)
PWR BWR ww 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 475 197 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 14x,14/15x15 7x7 j
16x16/17x17 8x8 l
Maximum active fuel i
length, inches 144 144
- ~
Maximum specific power, kw/kgU 40 27 Maximum burnup, MWD /MTU 40,000 34,000 Min-imum cooling time, days 150 120 The PWR type assemblies may be shipped either with or without burnable poison rods or control rods.
2303 354
-a,.
w w
=.
e
Page 5 - Certificate No. 9010 - Revision No. 5 - 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.
..._,,g (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:
(i) 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 Company 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 the 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.
2303 155 eymas momag.-..w ee he
.e.w ww a-w-m--
,m.
am.
e,eee a me.e pen -
s
Page 6 - Certificate No. 9010 - Revision No. 5 - Docket No. 71-9010 3.
The helium coolant is considered part of the package contents. The radioactive limits specified in 71.35(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.
- 10. The neutron shielding tank shall be filled with a mixture of water and ethylene glycol (52% by weight).
- 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 containment 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 shall be as described in Section XVI of the I
Application.
- 15. The packaging shall be dasigned, procured, fabricated, accepted, main-tained, operated, and repaired in accordance with the NL Industry, Nuclear Division, Quality Assurance Plan for the Model NLI-1/2 spent fuel shipping cask.
- 16. All valves, fittings, seals, and relief devices shall be of the type, size, model, and manufacturer as indicated on the drawings.
- 17. 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 XIV when used in Configuration (B).
- 18. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b). Fabrication under the general license is not authorized.
- 19. Expiration date: March 31,1980.
2303
.i S6
Page 7 - Certificate No. 9010 - Revision No. 5 - Docket No. 71-9010 REFERENCES NL Indastries, Inc. application dated December 20, 1972.
Suppiements dated:
February 5, June 28, July 31, and November 30, 1973; January 10 and 29 and July 10, 1974; January 7 and February 11, 1975;
- q. m January 19 and December 22, 1976; and March 22, 1978.
FOR THE U.S. NUCLEAR REGULATORY COMtilSS10N 0
Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety
?
MAY 0 51979 Date:
i h
2303 357 l
e.==%*.ey 0
-~eemm-..n.
--...,~~<----.m
..