ML19343C168
| ML19343C168 | |
| Person / Time | |
|---|---|
| Site: | 07109145 |
| Issue date: | 02/09/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19343C167 | List: |
| References | |
| USA-9145-A, NUDOCS 8102180839 | |
| Download: ML19343C168 (7) | |
Text
4 O.
Form NRC<618 U.S. NUCLEAR REGULATORY CoMMISSloN CERTIFICATE OF COMPtJ 1LNCE 10 CF R 71 For Radioactrve Materials Packages 1.(al Cartificate Numeer 1.(b) Revisson No.
1.(c) Package Identification No.
1.(di Pages N. 1.(e) Total No. PW 9
9145 0
USA /9145/A 1
2
~
- 2. PREAM8LE 2.ta)
TNs cartsticate is W to sattsfy Sections 173.393a 173.394.173.395, and 173.396 of the oeperrment of Transportaten Haaercous Materials Regulations (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the oscartment of Transportation Dangerous Cargoes Reg.statsons (46 CFR 146-149), as amended.
2.tb) be packaging and cantents desenbar in item 5 be6ow, meets the safety standards set forth in Subpart C of Title 10. Code of Federas Regulations. Part 71, Packagmg of Racioactive Meteriais for Transport and Transportation of Radioactive Matened Under Certa.n Conditions.-
2.fc)
TNs certificate ooes not re4ieve the conssonor from comoeiance mtn any reovirement of the tgulations of the U.S. Deoartment of Transoortation or other acclicande regulatory.agences. induding the government of anY Country through or into wheCM the pectage will be transcmrted.
- 3. Thes certsficate is issued on the basis of a safety analysis report of the package design or acosication-3.(a)
Prepared by (Name and address):
3.(b)
Title and afontification of reoort or soodication:
Nuclear Packaging, Inc.
NUPAC application dated September 19, 1980, 815 South 28th Street as supplemented.
Tacoma, WA 98409 71-9130 3.(ci cocmet No.
7 ENCITIONS This certificate es conditonal upon the fulfilling of the roouarements of Sucoort O of 10 CFR 71. as apolicaose. and the conditions spoofied in item s n.4ow.
- 5. Gescr.otion of Packaging and Authonted Contents. Mocet Numoor. Fisasie Cass, other Conditens. and Feferences:
(a) Packaging (1) Model No.:
NUPAC 50-1.5L, NUPAC 50-2.5L, NUPAC 50-3.0L, and NUPAC 50-4.0L (2) Description A steel encased lead shielded casks for low specific activity radioactive material.
The casks are right circular cylinder with a 48.5 inch inside diameter by 52.5 inch inside high cavity. The walls of the casks contain a lead thMkness ranging from 1.25 to 3.75 inches encased in 3/8-inch thick steel shells.
The bottom and top covers of the cask are made up of two, steel plates ranging in thickness from 1.00 to 3.00 inches.
The primary cask lid is secured to the cylindrical cask body by eight,1-inch rachet binders. A secondary cask lid is centered in the primary lid and is secured to the primary lid with eight, 3/4-inch studs and nuts.
Each lid is provided with a Neoprene gasket seal.
The cask is provided with four equally spaced lifting / tie down devices.
Cask gross weight ranged from 13,200 to 28,900 pounds.
(3) Drawing The packaging is fabricated in accordance with Nuclear Packaging, Inc.
Drawing No. X-20-2010, Sheets 1 and 2. Revision B.
s1oe380339:
s Page 2 - Certificate No. 9145 - Revision No. 0 - Docket No. 71-9145 (b) Contents (1) Type and form of material Solidified resins contained in secondary sealed containers meeting the requirements pf low specific activity radioactive material.
(2) Maximum quantity of material per package Greater than Type A quantities of radioactive material.
6.
The package authorized by this certificate shall be transported on a vehicle, railroad car, aircraft, inland water craft, or hold or deck of a seagoing vessel assigned for sole use of the licensee.
7.
Lid lifting devices shall be covered prior to transport to prevent its use as tie-down devices.
8.
The cask body and each cask lid shall be marked in accordance with 10 CFR 971.53(c).
9.
The package authorized for use by this certificate is hereby approved for use under license provision of 10 CFR 571.12(b).
10.
Expiration date:
February 28, 1986.
REFERENCES Nuclear Packaging, Inc. application dated September 19, 1980.
Supplements dated:
December 12 and 18, 1980 FOR THE U.S. NUCLEAR REGULATORY COMMISSION
[
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety FEB 0 91981 Date:
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6 U.S. Nuclear Regulatory Commission Division of Fuel Cycle and Material Safety Safety Evaluation by the Transportation Certification Branch NUCLEAR PACKAGING, INCORPORATED, MODEL NO. NUPAC 50 CASKS
SUMMARY
By application dated September 19, 1980, as amended, Nuclear Packaging, Incorporated (NuPac) requested approval to deliver low specific activity material to a carrier for transport in the Model No. NUPAC 50 shipping casks.
Based on the statements and representations as contained in the application, as amended, we have concluded that the contents and packaging meet the require-ments of 10 CFR Part 71 subject to the conditions stated below.
SUBMITTALS 1.
NuPac application dated September 19, 1980.
2.
NuPac supplement dated December 12, 1980.
3.
NuPac supplement dated December 18, 1980.
DRAWIN3 The packagings are fabricated in accordance with Nuclear Packaging Inc. Drawing Nos. X-20-2010, Sheets 1 and 2, Revision B.
PACKAGING DESCRIPTIONS A steel encased lead shielded casks for low specific activity radioactive material. The casks are right circular cylinder with a 48.5 inch inside diameter by 52.5 inch inside high cavity. The walls of the casks contain a lead thickness ranging from 1.25 to 3.75 inches encased in 3/8-inch thick-steel shells. The bottom and top covers of the cask are made up of two, steel plates ranging in thickness from 1.00 to 3.00 inches.
The primary cask lid is secured to the cylindrical cask body by eight,1-inch rachet binders. A secondary cask lid is centered in the primary lid and is secured to the primary lid with eight, 3/4-inch studs and nuts.
Each lid is provided with a Neoprene gasket seal.
The cask is provided with four equally spaced lifting / tie down devices.
Model No.
Le'ad thickness, in Cover thickness, in Gross Weight, lbs NUPAC 50-1.5L 1.5 2.25 13,163 NUPAC 50-2.5L 2.25 4.0 19,325 NUPAC 50-3.0L 2.75 4.5 22,050 NUPAC 50-4.0L 3.75 6.0 28,815
e
% PACKACE CONTENTS (A) Type and form of material Solidified resins contained in secondary sealed containers meeting the requirements of low specific activity radioactive material.
(B)
Maximum quantity of material per package B
Greater than Type A quantities of radioactive material.
CONTAINMEE The primary containment vessel is the inner cask shell and its closures. The primary containment vessel is sealed at top end with a primary and secondary cask lid each sealed with Neoprene gaskets. The botton end is welded closed to a steel plate. Adequacy of the containment system to meet Regulatory Guide 7.4 was demonstrated by a full scale test.
STRUCTURAL The applicant has performed various structural antlyses, engineering evalu-ations, and drop test to satisfactorily demonstrate the package has adequate structural integrity to meet the requirements of 10 CFR Part 71. The staff agrees with the applicant's conclusion that the packages have adequate structural integrity to meet the requirements of 10 CFR Part 71 subject to the conditions listed below.
A.
General Standards for All Packaging Chemical and Galvanic Reaction There is no significant chemical, galvanic, or other reaction among the packaging components, or between the packaging components and the package contents.
Positive Cicsure l
Inadvertent opening of the package is prevented by means of positive closure devices. There are no other penetrations to the containment vessel.
Liftino Devices l
(1) Four lifting lugs are shown by analysis to be capable of l
lifting three times the maximum package weight without i
exceeding material yield stress in any material of the l
packaging.
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. (2)
It is also shown by analysis that the primary and secondary lid lifting devices are capable of supporting three times the weight of lid and any attachments without generating stress in any mater'.al of the lid in excess of its yield strength.
(3) The requirements of covering the lid lifting devices are met by imposing a licensing condition in the Certificate of Compliance.
(4) The staff agrees with the applicant's conclusion that failure of lifting devices under excessive loaG would not result in any loss of packaging effectiveness or release of radioactive materials.
Tie-Dcwn Devices Applicant has shown by analysis that the tie-down devices which are strucutural parts of the packages are adequately designed to meet the regulatory requirements of 10 CFR 571.31.
B.
Structural Standards for Tyoe B and Large Quantity Packaging Load Resistance The packages are shown by analysis to be capable of withstanding statically five times of its fully loaded weight uniformly distributed along its length without generating stress in any material of the packagings in excess of their yield strength.
External Pressure Applicant has shown by analysis that the packaging designs meet the i
regulatory requirement with a large safety margin.
C.
Normal Conditions of Transport Heat The maximum package equibrium temperature has been estimated to be 1760F. The effects of this temperature increase from the room tem-perature on material properties are insignificant and on stresses are not expected to cause the stresses to exceed material yield stress.
Cold l
The stresses caused by themal contraction under the cold (-40cF) t l
environment are...dged not to reduce packaging effectiveness substantially.
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. Pressu-e, The cask containment vessels have been shown to withstand atmospheric pressure considerably greater than 0.5 times standard atmospheric pressure.
Vibration The vibration loading is judged not to have significant effects on packaging safety.
Water Spray Water spray will have no effect on the packages.
Free Drop The applicant's lead slump analysis results under the end drop impact loading may be nonconservative (underestimate lead slump) because the dynamic material strength values used were for higher drops. However, the stepped design of the package ends provides the maximum allowable slump distance of 0.3 v-1.625 inches, which exceed greatly the analytically obtained maximum lead slump distance of 0.141-inch.
A top corner drop test of the package was performed to show that the design in the seal area is adequate to meet the containment requirement.
The test results show that only small deformation of 0.06-inch was observed in the lid spacer ring / cask lip area. The seal remained leak-tight.
The applicant has shown by analysis that the lid rachet binders have sufficient strength to withstand a top end oblique drop impact loading with the package C.G. directly above the point of impact.
The packaging is labricated mainly from A-516, Grade 70 carbon steel.
Fracture failure under the drop impact loading at a cold temperature environment is judged adequate for the shipment of 1.SA materials.
Based on these calculations / evaluations / licensing conditions and engineering judgements, the staff has concluded that under the drop impact loading, the packagings effectiveness will not be substantially reduced.
Carser Droo Not applicable for this design case.
Penetration The staff agrees with the applicant's judgement that this regualtory loading has insignificant adverse effects on the package design.
s l
! Comoression Not applicable to the present design case.
SHIELDING The ability of the packagings to meet the shielding requirements of 49 CFR 9173.3931 or j will be demonstrated prior to each shipment by taking actual radiation measurements.
Independent staff calculations show that a 0.141-inch gap at the top of the cask due to the Normal Conditions of Transport. conditions will result in no significant increase in radiation levels.
CONDITIONS The safety of the cask was confirmed by the Transportation Certification Branch on the basis of the following conditions:
1.
The package authorized by this certificate shall be transoorted on a vehicle, railroad car, aircraft, inland water craft, or hold or deck of a seagoing vessel assigned for sole use of the licensee.
2.
Lid lifting devices shall be covered prior to transport to prevent its use as tie-down devices.
/J C ries E.
cDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety i
Date:
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