ML19296D561
| ML19296D561 | |
| Person / Time | |
|---|---|
| Site: | 07106387 |
| Issue date: | 02/20/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19296D557 | List: |
| References | |
| NUDOCS 8003050245 | |
| Download: ML19296D561 (5) | |
Text
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Form NRC418 U.S. NUCLE AR REGULATORY COMMISSION U 5' CERTIFICATE OF COMPLIANCE 10 Cl R 71 For Radioactive Materials Packages 1.(a C tificate Number 1.(b) Revisi n No.
1.(c) Pack eie iai N.
1.(d) P es No. l.(e) Total No. Pa s
- 2. PRE AMB LE 2.(a)
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 170-189 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), n.
mendas.
2.(b)
The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10, Code of Federal Regulations, Part 71," Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions /*
2.f 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 will 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:
Battelle Pacific Northwest Battelle Pacific Northwest Laboratories application Laboratories dated November 24, 1971, as supplemented.
Battelle Boulevard 71-6387 Richland, Washington 99352 3.(c) oocust No.
4 CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart O of 10 CFR 71, as applicable, and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorised Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a)
Packaging (1) Model No.: Model 60 (2) Description A metal " birdcage" enclosing a steel containment vessel for non-irradiated fuel pins. The stainless steel containment vessel is a 6-inch diameter, 101-1/4-inch long, Schedule 40 pipe. One end is closed with a 1-inch thick cover plate, bolted with eight 3/4-inch diameter bolts to a welded,150-pound, neck type flange. The gasket is a Flexitallic type, coiral wound, stainless steel, asbestos filter. The cover plate it fitted with 3 rupture disk assembly designed for up to 300 psi.
The containment vessel is centered inside a metal " birdcage" (18"x18"xil2.5", prismatic, cage frame made of 1-1/2"xi-1/2"x1/4" angle iron), supported by six 0.188-inch steel welded perpendicular to its longitudinal axis and equally spaced along its body.and by four Schedule 80 SS pipe spokes at each end. The outer spacer cage is covered with expanded steel mesh.
The loaded container weight is approximately 1,000 pounds.
o
~
8003050
Page 2 - Certificate No. 6387 - Revision No. 5 - Docket No. 71-6387 5.(a)
Packaging (Continued)
(3) Drawings The packaging is constructed in accordance with Drawing No. H-3-32429 (7 sheets), shown in Figuree ' through 9 in Hanford Engineering Development Laboratory Report No. TC-138, Rev.1, January 1978, and Hanford Engineering development Laboratory Drawings Nos. H-3-42514, Rev. 0; H-3-39691, Sheet 1, Rev. I and Sheet 2, Rev. 0; and H-3-44280, Rev. O.
(b) Contents (1) Type and form of material (i) Nonfissile radioactive material, in capsules which meet the requirements of special form material as defined in 10 CFR 571.4(o).
(ii) Unirradiated fuel pins containing mixed Pu02 in depleted or natural UO2 or Th02 as pressed sintered pellets of the following specification:
Pellet diameter, inch 0.19 to 0.205 Pin tiameter, inch 0.22 to 0.24 Maximum fuel length, inches 37.0 Maximum Pu0, w/o 31 2
Maximum U-235 enrichment, w/o 0.72 Minimum Pu-240 enrichment, w/o 10 Cladding material SS Minimum cladding thickness, inch 0.01 E in U02 enriched to (iii) Unirradiated fuel pins containing mixed Pu02 any degree in the U-235 isotope; Th02 may be substituted for depleted or natural UO ; plutonium or uranium carbides and 2
nitrides are allowed. All of the above as solid pellets of the following specifications:
Maximum pin diameter, inch 0.600 Maximum fuel length, inch 37 Minimum Pu-240 enrichment in Pu0, w/o 10 2
Maximum Pu-241 content
<1/2 content of Pu-240 Cladding material SS Minimum cladding thickness, inch
- 0. 01 0
( v) Pu02 and U02 enriched in the U-235 isotope in fuel pins or capsules which meet the requirements of special form material as defined in 10 CFR 571.4(o).
Page 3 - Certificate No. 6387 - Revision No. 5 - Docket No. 71-6387 5(b) (b)
Contents (Continued)
(v) U-233 in any solid physical or chemical form with any moderation in capsules which meet the requirements of special form material as defined in 10 CFR 571.4(o).
(vi) Np-237 and Am-241 in any solid physical or chemical form with any moderation in capsules which meet the requirements of special form material as defined in 10 CFR 571.4(o).
(vii) Pu-241 (in. isolated form), Am-242, Cm-243, Cm-244, Cm-245, Cf-249 and Cf-251 in any solid physical or chemical form with any moderation in capsules which meet the requirements of special form material as defined in 10 CFR 571.4(o).
(viii) Pu-241 (non-isolated form), Pu-238, Pu-239, Pu-240 and U-235 in any solid physical or chemical form; provided the Pu-241 content of the plutonium does not exceed 50% of'the Pu-240 content in capsules which meet the requirements of special form material as defined in 10 CFR 571.4(o).
(2) Maximum quantity of material per package The maximum package heat load shall not excecd 12.3 watts /ft of fuel length with the maximum package heat load not to exceed 37.0 watts, and plutonium in excess of twenty (20) curies per package must be in the form of metal, metal alloy or reactor fuel elements; and:
(i) For the contents described in 5(b)(1)(ii), 120 fuel pins. For the contents described in 5(b)(1)(iii) and constrained in appropriate pin holders as shown in drawings specified in 5(a)(3), the maximum in U02 anywhere fissile density shall not exceed 2.0 kg/ft for Pu02 along the length of the package.
(ii) For the contents described in 5(b)(1)(iv): Greater than Type A quantity of radioactive material and fissile material contents not to exceed the generally licensed mass limits as specified in 571.ll(a) of 10 CFR Part 71.
(iiil For the contents described in 5(b)(1)(v):
280 grams.
(iv) For the contents described in 5(b)(1)(vi): 15 kgs total.
(v) For the contents described in 5(b)(1)(vii):
3 grams total.
(vi) For the contents described in 5(b)(1)(viii): 900 grams fissile.
Page 4 - Certificate No. 6387 - Revision No. 5 - Docket No. 71-6387 5.
(Continued)
(c) Fissile Class II and III (1) Minimum transport index to be shown on label for Class II.
(i)
For contents described in 5(b)(1)(ii) and limited in 5(b)(2)(i):
0.4 (ii)
For contents described in 5(b)(1)(iii) and limited in 5(b)(2)(i):
7.0 (iii)
For contents described in 5(b)(1)(v) and limited in 5(b)(2)(iii):
1.3 (iv)
For contents described in 5(b)(1)(vi) and limited in 5(b)(2)(iv):
0.2 (v)
For contents described in 5(b)(1-)(vii) and limited in 5(b)(2)(v):
0.6 (vi)
For contents described in 5(b)(1)(viii) and limited in 5(b)(2)(vi):
Maximum grams fissile Transport per container Index 150 0.1 500 1.3 900 7.0 (2) Maximum number of packages per shipment for Class III Contents described in 5(b)(i)(iv) and limited in 5(b)(2)(ii):
One (1) 6.
For mixtures of isotopes specified in 5(b)(1)(viii) and 5(b)(1)(v) and limited in 5(b)(2)(vi), 5(c)(1)(vi), 5(b)(2)(iii) and 5(c)(1)(iii) the sum of the ratios of the content masses to their respective approved mass limits shall not exceed unity.
For the contents specified in 5(b)(1)(iii) and 5(b)(1)(ii) and limited in 5(b)(2)(1) 7.
and 5(c)(1)(ii) nitrides and carbides may be shipped under the same limits as oxides.
The fuel pins shall be positioned in a stainless steel pin holder providing a close packed 5.7-inch diameter array, and:
(a) For pin holders containing between 58 and 120 pins in stainless steel tubes the minimum tube wall thickness shall be 0.035 inches; (b)
For pin holders containing betweer. 35 and 57 pins in stainless steel tubes, the minimum tube wall thickness shall be 0.050 inches.
Page 5 - Certificate No. 6387 - Revision No. 5 - Docket No. 71-6387 8.
The packaging shall be equipped with a FIKE Assembly Number 1/2 SP 10A rupture unit having a muffled outlet, 304 SS body, and nickel rupture disc to burst at less than 300 psi.
9.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
- 10. Expiration date: June 30,1980.
REFERENCES Hanford Engineering Development Laboratory letter dated March 19, 1979.
FOR THE CONTENTS DESCRIBED IN 5(b)(1)(ii) and 5(b)(1)(iv):
Battelle Pacific Northwest Laboratories' application dated November 24, 1971.
Supplement dated: July 18,1972.
Hanford Engineering Development Laboratory letter dated June 13, 1975.
FOR THE CONTENTS DESCRIBED IN 5(b)(1)(i), 5(b)(1)(iii), 5(b)(1)(v), 5(b)(1)(vi),
5(D)(1) vii
, AND 5(b)(1)(viii Hanford Engineering Development Laboratory Report No. TC-138, Rev.1, January 1978.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date: FEB 2 01930
.