ML19260C192
| ML19260C192 | |
| Person / Time | |
|---|---|
| Site: | 07109001 |
| Issue date: | 12/10/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19260C190 | List: |
| References | |
| NUDOCS 7912260049 | |
| Download: ML19260C192 (6) | |
Text
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4 Forrn NRC418 U.S. NUCt. EAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE 10 C R 1 For Radioactive Materials Packages 1Ja) Certificate Number 1.(b) Revision No.
1.(c) Package identification No.
1.(d) Pages No. 1.(e) Total No. Pages 9001 9
USA /9001/B( )F 1
6 i
- 2. PREAMBLE 2.(s)
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 am=Med.
2.lb)
The n,ckagire and conte.its described in item 5 below, meets the safety staadards set forth in Subpart C of Title 10, Code of Federal Regulations. Pars 71, " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Materi41 Unoer Certain Conoitions."
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 wi!! be transported.
- 3. This 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:
General Electric Company General Electric Company application dated 175 Curtner Avenue October 8, 1979.
San Jose, CA 95125 3.(c)
Docket No. 71-3001
- 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 t elow.
- 5. Description of Packaging and Authorized Contents. Model Number, Fissile Class, Othe Conditions, and
References:
(a) Packaging (1) Model No.-
IF-300 (2) Description A stainless steel encased, depleted uranium shielded cask. The cask is cylindrical in shape, 64 inches in diame':er and a maximum of 210 inches long with uaximum cavity dimensions of 37-1/2 inches in diameter by 180-1/4 inches lonJ.
Shielding is provided by 4 inches of depleted uranium, 2-1/8 inches of stainless steel and a minimum af 4-1/2 inches of water.
Two closure heads are provided for the shipment of BWR and PWR fuel assemblies.
The heads are 304 stainless steel forgings and end plates which encase tne 3-inch thick depleted uranium shielding.
The closure heads are secured to the cask body by means of 32,1-3/4 inch studs. The cask is sealed with a metallic ring gasket.
The cavity is penetrated by a vent line at the top and a, drain line at the bottom. These lines are sealed by bellows seal stainless steel globe valves and valved quick-disconnect couplings. The vent line is also equipped with a 375 psig relief valve. All valves are housed in protected boxes on the cask exter*
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Page 2 - Certificate No. 9001 - Revision No. 9 - Docket No. 71-9001 5.
(a) Packaging (continued)
(2) Description (continued)
Neutron shielding is provided by a liquid-filled, thin-walled, corrugated containment on the cask exterior.
This cylindrica! structure is separated into two longitudinal ccmpartments, each equipped with two expansion tanks, fill and relief valves.
The fill line from each compartment is terminated by a stainless steel globe valve in a protected box (separate from cavity boxes) on the cask exterior.
The vent line from each compartment goes to an expansion tank which is provided with a pressure relief valve set at 200 psig.
The cask has two types of fuel baskets which can be interchanged to accommodate various fuels.
The PWR basket holds 7 assemblies, the BWR basket hold 18 assemblies.
The BWR fuel basket may be provided with supplementary shielding (depleted uranium) near the cask closure.
The cask is shipped horizontally with the bottom supported in a tipping cradle between two pedestals and the upper end resting in a semi-circular saddle; the upper end is pinned to the saddle.
The cask supports are welded to the framing of a 37-1/2-foot long by 8-foot wide. structural steel skid.
The skid also holds the cask cooling system which consists of two diesel engines driving two blowers which discharge into common ducting.
Four ducts run the length of the cask and direct cooling air to the corrugated surface.
Operation of the auxiliary cooling system is not a requiremelt of this package approval.
The entirc cask and cooling system is covered by a retractable aluminen enclosure.
Access to the enclosure is sia locked panels in the side and a locked doo-in one end.
Although the hciel No. IF-300 cask can be tra.1 sported for short distances on the highway, its principal mode of transportation is by railroad.
The gross seight of the cask is approximately 140,000 pounds.
The skid and other external components weigh approximately 35,000 pounds.
(3) Drawing The Model No. IF-300 shipping cask is described by the following General Electric Company Drawing No.:
159C5238-Sheets 1 thru 2, Rev. 2; Sheet 3, Rev. 3; Sheets 4 thru 5, Rev. 4; Sneet 6, Rev. 5; Sheet 7, Rev. 3; Sheet 8, Rev. 3 or 4; Sheet 9, Rev. 3; Sheet 10, Rev. 5; and Sheet 11, Rev. 2.
(b) Contents - water as primary coolant (1) Type and form of material Irradiated PWR or BWR uranium oxide fuel assemblies.
The specific power of each fuel assembly shall not exceed 40 kw/kgU and the burnup of each fuel assembly shall not exceed 35,000 MWD /MTU.
The minimum cooling time of each assembly shall be no less than 120 days.
Prior to irradiation, the PWR and BWR fuel assemblies have the following dimensions and specifications:
a
Page.3 - Certificate No. 9001 - Ravisinn !-
' No. 71-9001 5.
(b) Contents-water as primary coolata sued)
PWR BWR Fuel form Clad u Clad UO2 pellets Cladding material Zr 55 Zr or SS Maximum initial U content / assembly, kg 465 198 Maximum initial U-235 enrichment, w/o 4.0 3.5 Maximum bundle cross section, inches 8.75 5.75 Fuel pin array 14x14/15x15 7x7 Fuel diameter, inch 0.380-0.450 0.500-0.600 Fuel pin pitch range, inch 0.502-0.582 0.647-0.809 Maximum active fuel length, inches 145 146 The assembiies may be shipped with or without burnable poison rods or control rods.
(2) Maximum quanity of material per package Maximum decay heat per package not to exceed 210,000 Btu /hr.
Maximum 37,500/ Btu /hr/PWR assembly.
Maximum 14,600/ Btu /hr/BWR assembly.
Seven (7) PWR fuel assemblies, or eighteen (18) BWR fuel assemblies.
Above assetblies to be contained in their respective fuel baskets are shown in GE Drawing No. 159C5238-Sheet 6, Rev 5.
(c) Contents - air as primary coolant (1) Type and form of material Irradiated PWR and BWR uranium oxide fuel assemblies.
The specific power of each fuel assembly shall not exceed 40 Kw/KgU and the burnup of each fuel assembly shall not exceed 35,000 MWD /MTU.
The mini, mum cooling tirae of each assembly shall be no less than 120 days.
Prior to irradiation, the BWR and PWR fuel assemblies shall have the following dimensions and specifications:
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Page 4 - Certificate No. 9001 - Revision No. 9 - Docket No. 71-9001 5.
(c) Contents-air as primary coolant (continued)
PWR BWR Fuel form Clad U02 pellets Clad UO pellets 2
Cladding material Zr or bS Zr or SS Maximum initial U content / assembly, kg 465 198 i
Maximum in tial U-235 i
enrichment, w/o 4.0 3.5 Maximum bundle cross section, inches 8.75 5.75 Fuci pin array 14x14/15x15 7x7 Fuel diameter, inch 0.380-0.460 0.500-0.600 Fuel pin pitch range, inch 0.502-0.581 0.647-0.809 Maximum active fuel length, inches 143 146 The assemblies may be shipped with or without burnable poison rods or control rods.
(2) Maximum et.sntity of material per package Maximum decay heat per package not to exceed 40,000 Btu /hr.
Maximum 5,725 Btu /hr/PWR assembly.
Maximum 2,225 Btu /hr/BWR assembly.
Seven (7) PWR fuel assemblies, or eighteen (18) BWR fuel assemblies.
Above assenblies tc be contained in their respective fuel baskets as shcwn in GE Oraving No. 159C5238-Sheet 6, Rev. 5.
(d) Unloaded package - contents and maximum quantity of material Greater than a Type A quantity of residual radioactive material consisting of mixed-fission and activation products achering to interior cavity and fuel basket surfaces.
(e) Fissile Class I
6.
The end of life (after irradiation), fuel pin pressure shall not exceed 1,800 psia, at 900 F.
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Page 5 - Certificate No. 9001 - Revision No. 9 - Docket No. 71-9001 7.
The maximum gross weight of the cavity contents shall not exceed 21,000 pounds.
l 8.
(a) For the contents described in 5(b) (water coolant) the cavity fill specifications shall include the following:
A 21.0 + 1.0 - 0.5 cu ft cavity air void shall be established for PWR and BWR loadings.
These air voids are established when the bulk water temperature is at 100 F for both the PWR and BWR loadings.
If less than the maximum number of fuel assemblies is loaded into the basket, a void displacement equivalent to the missing fuel assemblies shall be inserted into the basket.
In addition, the licensee shall take sufficient time-temperature-pressure data tc show that the cavity pressure will not exceed 346 psig during a 130 F day with no auxiliary cooling.
Under freezing conditions, the minimum heat load shall be 36,400 Btu /hr when water is used as the primary cavity coolant.
(b) For the contents described in 5(c) (air coolar.t) the cavity fill specifications shall include the following: An air void shall be established such that not more than 1.0 cu ft of water (corresponding to a bulk water temperature of 70 F) remains in the cavity.
The licensee shall take sufficient time-temperature-pressure data tc. ensure that the cavity pressure will not exceed 45 psig, and that the average cavity wall temperature will not exceed 210 F during tne l?0 F day with no auxilary cooling.
9.
A determination shall be made for each water coolant shipment (for contents described in 5(b) that the total radioactivity of the primary coolant will not exceed, during the anticipated period of transport, the limits specified in 10 CFR S71.36(a)(2).
This determination shall include monitoring of the coolant and verification of tie coolant activity upoi arrival of the package at its destination.
Records of suct determinations shall be maintained for a period of two years after its generatior.
10.
For the contents des:ribed in 5(c) and 5(d), the air coolant is considered part af the package contents.
The radioactivity limits specified in 10 CFR 971.35(a)(4) do not apply.
11.
Prior to each shipmert, the licensee shall confirm that the cask is properly sealed by testing as Subsection 11.3.3.1.
l 12.
The cask concents shall be so limited that under nermal conditions of transport, lil times the neutron dote rate plus 11.3 times the gamma dose rate will not exceed i,000 mrem /hr at three (3) feet from the external surface of the cask.
13.
The neutron shielding tanks shall be filled with water during the months of May through October and approximately a 50/50 volume percent mixture of ethylene glycol and water during the months of October through May if the total package decay necc is greater than 183,400 BTV/hr (70% of design basis).
If the total package decay neat is less than 183,400 BTU /hr the ethylene glycol and water mixture may remain in place all year.
14.
In addition the requirements of Subpart D of 10 CFR Part 71, each package prior to first use shall meet all of the acwptance tests and criteria specified in Subsection 6.7.6.2.
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Page 6 - Certificate No. 9001 - Revision No. 0 - Docket No. 71-9001 15.
The maximum allowable heat load shall be documented for each cask and conspicuously and durably marked on the cask.
16.
Each cevity relief valve, typical glove valves, and typical shielding tank (barrel expansion tank) relief valves shall be tested as stated in Subsections 6.5.3.3, 6.6.1.1, and 6.6.1.2.
In lieu of the requirements of 10 CFR 671.54(h), valve testing and maintenance frequency shall be as stated in Subsections 6.5.3.4, 6.6.2.1, and 6.6.2.2 except l
during periods of cask inactivity.
During inactise periods the maintenance and testing frequency may be disregarded provided that the package is brought into full compliance with these requirements prior to the next use of the package.
l 17.
The cask cavity shall te equipped with a Target Rock 73J pressure relief valve set at a pressure of 375 psig (450 F). The valve is shown in Target Rock Corporation Drawing No. 73J-001, Rev. J.
I 18.
The uranium shielding material shall be separated from all steel surfaces with a minimum copper thickness of 4-mils, except that the stud bolts attaching the shield assemblies to top of the BWR basket shall be coated with a minimum of 1/2 mil cf copper.
19.
For casks using air.ts the primary coolant, the cavity pressure relief valve specified in Item 16 shall be 'nstalled and operating during the cooldown prior to unloading.
20.
No shutoff valve shall be installed between each neutron shield tank and its respective thermal expansion tank.
21.
The package authoriz2d by the certificate is here.1y approved for use under the general license prosisions of 10 CFR S71.12(b).
22.
Expiration date:
December 31, 1984 REFERENCES General Electric Company consolidated application dated October 8, 1979.
l.
Documentation of maximum package heat load as determinad by Item 15 above.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION kd4 !
Charles E. MacDonald, Chief Transportation Certification branch Division of Fuel Cycle and Material Safety DEC 101979 Dh a
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