ML19329F801
| ML19329F801 | |
| Person / Time | |
|---|---|
| Site: | 07109009 |
| Issue date: | 06/13/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19329F799 | List: |
| References | |
| NUDOCS 8007110166 | |
| Download: ML19329F801 (4) | |
Text
.
O Fom NRCUS U.S. NUCLE AR REGULATORY CoMMISTION j$73',
CERTIFICATE OF COMPLIANCE For Radioactive Materials Packages 1.al Cat'iciere Wurnbar 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.(e) Total 8. Pages 9:09 8
USA /9009/B( )F 1
2.PAEAusLE 2.W This certificate is issued to satisfy Sections 173.393a.173.394,173.395, and 173.396 of the Department of T:ensportation Hazardous Masarisis Regulations (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-10e and 146-19-100 of the Deperurent of Transportesion Dangerous Cargoes R.egulations (46 CFR 146-149), as amended.
2.ltj The packaging and contents desertbed in item 5 below, meets the safety standards set forth in Suboert C of Title 10. Code of
- Feeeral Residstions. Port 71. " Packaging of Radioactive Meterials for Transport and Transportation of Radioactive Meterial Under Corseen Conditions."
2.(si This artificete does not rollows the conesanor from corneliance with any requerement of the regulations of the U.S. Department of Trasporisoon or other soplis.able regulatory agences, including the government of any country through or into which the am*6=T*
- s5 he transpersed.
- 3. T1nis casiraceae is issued on the basis of a safety analyus report of the pe.* age design or application-3.W Preserud by (Namie and addresop 3.(b)
Title and identification of report or' application:
General Electric Company General Electric Company application dated P.O. Btx 780 March 12,1973, as supplemented.
nHlaringcon, f4C 28401
- 3. ten Docket No.
- 4. COND TIONS This certraste is senditionel upon the fulfiiling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specif'ad
'an ' mns 5 belous.
a
- 3. Osmucrcoce of Packassng and Authorized Crvtants Model Number, Fissile Cass, other Conditions. and References.
(a)
Packaging (1) Model No.:
FL 10-1
~
(2) Description e
Two,16-gage 55-gallon drums welded end to end, approximately 68 inches long and 22-1/2 inches in diameter. The outer drum closure shall be accomplished by at leasc a 12-gage bolt-locking ring with drop-forged lugs, one of which is threaded to receive at least 5/8-inch diameter bolt and lock nut. The pressure vessel support mechanism consists of wood supports, steel inner sleeve and nut ring to receive the containment vessel, and fire resistant phenolic foam, fonned in place to an average finished density of at least 8 pounds per cubic foot for the main body and 10 pounds per cubic foot for the cap. Gas relief holes shall be provided in the outer steel drum.
The containment vescel is a 304L stainless steel 5-inch Schedule 40 pipe, appmximately 53-1/2 inches long, with a 304L stainless steel 1/2-inch tnick welded bottom plate and a 304L stainless steel 300 pound slipon flange and blind flange which is fastened by eight, 3/4-inch steel bolts.
The flange closure is gasketed by'two flouroelastomer 0-rings with a pressure tap between the two 0-rings grooves.
During shipment, the 0-ring croove prassure tao 4 sealed with a pipe plug with threads wrapped in reflon tape. A 1/4-inch stainless steel valve is screwed into the blind flange of the containment vessel. The valve is sealed by a pipe cap 800 7110/lela
~
Itge 1 - Certificate No. 9009 - Revision No. 8 - Docket No. 71-9009 4
5.
(a:
(2*
Description (continued)
(tnreads wrapped with teflon tape) and is protected by a 2-1/2-inch high section 5-inch Schedule 40 pipe welded to the top of the flange. The packaging has a maximum gross weight of 515 lbs.
(3) Drawings The Model No. FL 10-1 package is described by International Nuclear Company (INCO) Drawing No. DSD-479-D, Rev. C, and the containment vessel described by INC0 Drawing No. DSD-480-D, Rev. C.
The containment vessel seal is described by INCO Drawing No. DED-169-B, Rev. 2.
(b) Centents (1) Type and form of material (i) Uranyl nitrate solutions having a con':entration of uranium 235 ar.d uranium 233 not exceeding 350 grams per liter and an H/U-235 atomic ratio not less than 80, provided that the U-233 and plutonium content is not more than 1% of the U-235 content; or (ii) Uranyl nitrate solutions having a combined concentration of uranium 233 and uranium 235 not exceeding 250 grams per liter and an H to fissile material atomic ratio not less than 80 provided (1) the U-233 content is not greater than 20% of the combined U-233 and U-235 content, and (2) the plutonium content is not more than 1% of the combined U-233 or U-235 content; or (iii)
Plutonium nitrate solutions having a concentration not exceeding 250 grams fissile plutonium per liter; or Uranyl sulfate solution (U0 50 ) containing uranium-235; or (iv) 2 %
(v) Dry compounds and mixtures of fissile plutonium-uranium-235; or (vi) Mixed U-Pu oxide interspersed with graphite or silicon carbide plus plastic packing material.
(2) Maximum quantity of material per package Plutonium in excess of twenty (20) curies per package must be in the form of metal, metal alloy, or reactor elements; or must be in accordance with Item 9 below; and:
(1)
For the contents described in 5(b)(1)(1), (ii), and (iii):
Maximum decay heat load not to exceed 21 watts, and 10.5 liters of solution.
e e
- age 3 - Certificate No. 9009 - Revision No. 8 - Docket No. 71-9009 E..~ b ) Contents (continued) l (ii)
For the contents described in 5(b)(1)(iv):
I~
Maximum decay heat load not to exceed 18 watts and 950 grams fissile material.
(iii) For the contents described in 5(b)(1)(v):
Maximum decay heat load not to exceed 30 watts, and 4.5 kilograms fissile material.
(iv) For the contents described in 5(b)(1)(vi):
Maximum decay heat load not to exceed 10 watts and 300 grams fissile material.
(c) Fissile Class I
E.
The solution contents of the package shall be contained with a bottle having one of the following specifications:
(i) Slit vent polyethylene bottle per Drawing No. CAPE-1170-37, (ii) Ouo-vent polyethylene bottle per Nuclear Fuel Services, Inc., Specification U-l and Drawing No. 58-U-740, or (iii) Stainless steel bottle as shown on General Electric Company Drawing Nos. FRO-140 and FRO-140A.
T.
The polyethylene bottles may be packaged within the matal inner container described by Chester-Jensen Company, Inc., Orawing Nos.1092M-1,1093M-1,1095M.-l and 1096M-1, Issue 1, dated April 26, 1971.
1.
The packaging for the polyethylene bottles shall include a flexibile restraining device (such as recommended in ARH-1819 " Vibration Testing of L-3 and L-10 Shipping Containers") placed between the cap assembly of the polyethylene bottle and ths closure flange of the pressure vessel to assure that the polyethylene bottle will vibrate at the same frequency as the pressure vessel during transport.
3.
Dry compounds and mixtures which shall be packaged within sealed metal cans or DOT Specification 2R containers (49 CFR 5178.34); and placed within an inner container constructed and leak tested as specified on General Electric Illustration AFL 1105.
Following the gas leak testing specified on the Illustration, all inner container welds shall be leak tested using a liquid penetrant method in accordance with Article 5,Section V, ASME Code. Alternatively, the inner container shown in the Illustration r.ay be constructed of 300 series stainless stael pipe with an outside diameter of 4.503 + 0.031 inches with a wall thickness. ranging between 0.095 ~and 0.140 inch.
l 0.
A:pr:priate steps shall be taken to assure that from the time of sealing to the time f delivery to the consignee, the pressure in the containment vessel will not exceed i: psig.
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Page 4 - Certificate No. 9009 - Revision No. 8 - Docket No. 71-9009 s
11.
Prior to each shipment of more than Type A quantities of radioactive material, the space between the double 0-ring seal shall be tested at 100 psig and leak detection performed by a method capable of detecting a leak greater than 10 3 atm cc/sec at standard temperature and pressure.
No package with a detectable leak shall be delivered to i carrier for transport.
12.
In addition to the requirements of Subpart D of 10 CFR 71, a test shall be performed on each containment vessel and associated 1/4-inch SS valve (without its associated pipe cap) initially and once each year at 300 psig and the leak detection performed by a method capable of detecting a leak greater than 10 6 atm cc/sec at standard temperature and pressure. Any chamber that fails to pass the test shall be withdrawn from service and repaired to meet the test.
- 13. The fire resistant phenolic foam shall be in accordance with AEC Materials and Equipment Specification SP-9 or as modified by ORGDP Reports K/TL-729 and K/P-65675.
- 14. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
- 15. Expiration date: August 31, 1983.
REFERENCES General Electric Company application dated March 12, 1973.
Supplements dated: April 13,1973; March 21,1974; and April 16, 1979.
Westinghouse Electric Corporation supplements dated: October 3, 1979; and March 11, 1980.
Babcock and Wilco. Company supplement dated: May 14,1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION k
Charles. MacDona d, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety O 1 3 1980
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- .a Babcock &Wilcox Nuclear Materials Division
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i 6o9 North Warren Avenue, f.po!!o, Pa.15513 Telephone: (412) 842.o111
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chfi kfB03 May 14, 1980 Y ' '
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Mr. C. MacDonald, Chief MAY 2 7 ISM > Q Transportation Branch 5
HMss U.S. Nuclear Regulatory Comission man. sec7mn Office of Nuclear Material Safety & Safeguards Do c m c m ut
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Washington, D.C. 20555 g i I.u t W=
Dear Mr. MacDonald:
Pennsylvania Operations hereby requests an amendment to Certificate of Compliance No. 9009, Revision No. 7.
Specifically, we request that the dimensions of the alternate inner container constructed of 300 series stainless steel pipe (as given in Item 9 of the current Certificate) be revised to permit tubing or pipe with an Outside Diameter (0.D.) tolerance of + 0.031 inchet.
Also, we request that the wall thickness of this inner container be permitted to range between 0.095 and 0.140 inches.
The requested tolerance for the outside diameter is derived from the Standard Fractional Tolerances as specified in ASTM t'412/530. The requested range of acceptable wall thicknesses is s me.Mtent with that given in Illustration AFL-1105 and the alternou wall thickness currently authorized in Item 9 of the Certificate.
This amendment request is a clarification of acceptable dimensional requirements and does not affect the safety provided by the packaging.
Undar separate cover, a check in the amount of $150.00, payable to the U.S. Nuclear Regulatory Comission, has been fomarded to.Mr.
Douglas Weiss (NRC License Fee Management Branch) according to the requirements of 10 CFR 170.31 1C.
If go icve any cuestions rans rding this request, please contact me.
l.pplicant....f!# ""-"" sincerely, en.xx.a
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