ML20052B517

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Forwards IAEA Certificates USA/0220/AFT & J/74/AF & Requests Review of Contents of J/74/AF
ML20052B517
Person / Time
Site: 07109019
Issue date: 04/09/1982
From: Rawl R
TRANSPORTATION, DEPT. OF
To: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
20561, NUDOCS 8205030190
Download: ML20052B517 (14)


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9 DOCKETCLERK Mr. C. E. MacDonald Transportation Certification Branch q

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Nuclear Regulatory Conmissicn Washington, D.C.

20555

Dear Mr. MacDonald:

Enclosed are copies of International Atomic Energy Agency Certificates USA /0220/ AFT (revalidatingJ/79/AF)andJ/74/AF.

Certificate USA /0220/ AFT was issued partly on the basis of the similarity between J/79/AF and NBC Certificate of Conpliance No. 9019. We have been requested to revalidate J/74/AF which is for the same packaging but for a higher uranium-235 enrichment of the contents.

Please review the package contents specified in J/74/AF and let me know if these are suitable.

Sincerely, Richard R. RAWL Chief, Radioactive Materials Branch Office of Ilazardous Materials Regulation Materials Transportation Bureau Enclosures c(/} GC m nfQY i

n 8205030100

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IDENTIFICATION MARK J/74/AF COMPETENT AUTHORITY OF JAPAN CERTIFICATE OF APPROVAL OF PAC.KAGE DESIGN FOR THE TRANSPORT OF

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R~ADIOACTIVE MATERIALS k

ISSUED BY SCIENCE AND TECHNOLOGY AGENCY 2 2-1, KASUMIGASEKl. CHlYODA-KU. TOKYO. JAPAN

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0 SCIENCE AND TECHNOLOGY AGENCY 2-2-1 Kasumigaseki Chiyoda-ku, Tokyo, Japan l

l CERTIFICATE OF APPROVAL OF PACKAGE DESIGN l

FOR THE TRANSPORT OF RADI0 ACTIVE MATERIALS j

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l This is to certify, in response to the application -by Japan Nuclear Fuel Conversion Co., Lt'd. on February 13.

1981 that the Design of Package described herein satisfies the design requirements of Type A' Fissile Class II Package O

specified in Regulations for the Safe Transport of Radio-active Materials (International Atcmic Energy Agency, Safety Series NO.6,1973 Edition) i COMPETENT AUTHORITY IDENTIFICATION MARK: J/74/AF

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FEBRUARY 24,1981 Date Nobuhisa Akabane Director General, Nuclear Safety Bureau Science and Technology Agency Competent Authority of Japan for Packages of Nuclear Materials

1.

NAME OF PACKAGING BU-J 2.

SPECIFICATION OF CONTENT (1)

DESCRIPTION OF CONTENTS (i) Paterial cf Nuclear Fuel

Uranium 0xide l

(ii)

Initial Enrichment

Max. 12.18%

j (2) RESTRICTIONS ON CONTENTS (i) Total Weight of Nuclear Fuel

Max. 90 kg (ii) Total Activity
Max. 150 m Ci (iii) Total Heat Generation Rate
0 (iv) Burn Up Rate
0 (v) Cooling Time
0 3.

SPECIFICATION OF PACKAGING (1) TOTAL WEIGHT OF PACKAGE

Max. 210 kg (2) OUTER DIMENSION OF PACKAGING (i) Diameter
ca. 61 cm (ii) Height
ca. 88 cm (3) PATERIALS OF PACKAGING

_( i.)

Irner Container Inner Container Drum Can Steel ( Equivalent to SPHC or SPCC )

c Flange and Lid Steel (Equivalent to' 5541.)

Gasket Butyl Rubber Bolt and Nut

Steel ( Equivalent to SS41),

(ii) Outer Container Outer Container Drum Can Steel ( Equivalent to SP.HCorSPCC) w-

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Fastening Device

Steel (Equivalent to SS41)

Gasket

Natural Rubber Thermal Insulator
Pearlite-Alumina Cement (4) PACKAGE ILLUSTRATION (See the attached figure) 4.

TERMS OF CRITICALITY CLEARANCE Water-tightness of inner container have been certified by the tests necessary for fissile material package. 56 no: water in-leakage 5

is assumed, as the cond'ition of subc'riticality evaluation.

Therefore quality control and inspection regarding th,e water-tightnes.s of inner container shall be done.

5.

ASSUMED AMBIENT CONDITIONS (i) Ambient Temperature

38'C (ii)

Insolation Data

Table III of the IAEA Regulations 6.

RESTRICTIONS ON TRANSPORT (i) Allowable Number of Package 125 (ii) Arrangement

No R,estriction (iii) Mode of Transport Road and Sea 7.

INSTRUCTIONS ON USE AND MAINTENANCE OF PACKAG-ING (1)

The package shall be 1,ifted with a folklift truck.

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(2)

Gaskets of package shall be inspected bEfore each shipment, and shall be exchanged if necessary.

9 (3) Each package shall be inspected periodically to maintain the integrity.

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8.

ACTIONS PRIOR TO SHIPMENT

,Each package shall be checked for the following items before ship-ment (1) Visual inspection (2) Lifting test (3) Weight measurement (4) External surface contamination measurement (5) Radiation dose rate measurement (6) Subcriticality inspection (7) Inspection of nuclear fuel ma.terials 9.

THIS CERTIFICATE IS VALID TILL DECEMBER 7, 1983

10. THIS CERTIFICATE DOES NOT RELIEVE THE CONSIGN 0R FROM COMPLIANCE WITH ANY REQUIREMENT OF THE GOVERNMENT OF ANY COUNTRY THROUGH OR INTO WHICH THE PACKAGE WILL BE TRANSPORTED.

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SCIENCE AND TECHNOLOGY AGENCY 2-2-1 Kasumigascki Chiyoda-ku, Tokyo, Japan inia.Y 8. Z. '.

A. L KAFL.S.N CER'.?IFICATE OF APPROVAL OF PACKAGE DESIGN FOR THE TRANSPORT OF RADIOACTIVE MATERIALS This is to certify, in response to the application by Japan Nuclear Fuel Co., Ltd. on February 26, 1981 that the Design of Package described herein satisfies the design requirements of Type A Fissile Class II Package specified in Regulations for the Safe Transport of Radio-active Materials (International Atomic Energy Agency, Safety Series NO.6, 1973 Edition)

COMPETENT AUTHORITY IDENTIFICATION MARK: J/79/AF

,e March 23,1981

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Date Nobuhisa Aka Director General, Nuclear Safety Bureau Science and Technology Agency j

Competent Authority of Japan for Packages of Nuclear Materials

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1. NAME Ci PACKAGING
BU-J 4

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2. SPECIFICATION OF CONTENT (1) DESCRIPTION OF CONTENTS (i) Material of Nuclear Fuel
Uranium Oxide s

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(ii) Initial Enrichment ~

Max. 4.0%

5'i (2) RESTRICTIONS ON CONTENTS k

(i) Total Weight of Nuclear Fuel

Max. 90 Kg (ii) Total Activity
Max. 150 m Ci (iii) Total Heat Generation Rate
0 h3 (iv) Burn Up Rate
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(v) Cooling Time

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(vi) Physical properties

Solid (powder & pellets) a mj (vii) Maximum Contents Per Package
See Table - 1

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3. SPECIFICATION OF PACKAGING l

(1) TOTAL WEIGHT OF PACKAGE

Max. 210 Kg (2) OUTER DIMENSION OF PACKAGING (i) Diameter
ca. 61 cm El j

h, (ii) Height

ca. 88 cm (3) MATERIALS OF PACKAGING (i) Outer Container 2

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Outer Container Drum Can

Steel (Equivalent to SPHC or SPCC)

Fastening Device

Steel (Equivalent to SS41)

Gasket

Natural Rubber Thermal Insulator
Pearlite-Alumina Cement 4

(ii) Inner Container v

'M1 Inner Container Drum Can

Steel (Equivalent to 1

SPHC or SPCC) 4

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J/79/AF

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CERTIFICATE OF APPROVAL OF PACKAGE DESIGN

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2 ISSUED BY SCIINCE AND TECHNOLOGY AGENCY j

2-2-1, KASUMIGASEKI, CHIYODA-KU, TOKYO, JAPAN

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i Flango and Lid

Stool (Equivalent to SS4111 4

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3 Bolt and Nut M_

Steel (Equivalent to SS41; (iii) 2.5 or 5-gallon Uranium oxide Pails t

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(4) PACKAGE ILLUSTRATION (See the attached figure)

4. TERMS OF CRITICALITY CLEARANCE k;-

Water-tightness of inner container have been certified by

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the tests necessary for fissile material package.

So no water inleakage is assumed, as the condition of subcriticality j

evaluation.

Therefore quality control and inspection regarding i

28 the water-tightness of inner container shall be done.

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5. ASSUMED AMBIENT CONDITIONS 3

(i) Ambient Temperature

38 C (ii) Insolation Data
Table III of the g

IAEA Regulations 7

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6. RESTRICTIONS ON TRANSPORT

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(i) Allowable Number of Package

500
s (ii) Arrangement
No Restriction
7. INSTRUCTIONS ON USE AND MAINTENANCE OF PACKAGING (1) The package shall be lifted with a folklift truck.

(2) Gaskets of package shall be inspected before each shipment, and shall be exchanged if necessary.

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.y (3) Each package shall be inspected periodically to maintain

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the integrity.

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8. ACTIONS PRIOR TO SHIPMENT 3

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Each package shall be checked for the following items before 4

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(1) Visual inspection

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(2) Lifting test N

(3) Weight measurement 3

(4) External surface contamination measurement A

7, (5) Radiation dose rate measurement Q

(6) Subcriticality inspection 2

j (7) Inspection of nuclear fuel materials

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(8) The packages shall be loaded in such a way that they are 3j kept in position and will not fall off.

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9. THIS CERTIFICATE IS VALID TILL DECEMBER 19, 1983
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10. THIS CERTIFICATE DOES NOT RELIEVE THE CONSIGNOR FROM COMPLIANCE dil J

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OR INTO WHICH THE PACKAGE WILL BE TRANSPORTED.

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Table - 1

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Maximum Contents per Package A

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Maximum Quantity of Material per Package

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( Kg - UO2) 1 Pellets Powder j

2.7 or less 90.0 89.0

,7 3.0 76.2 89.O.

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3.2 68.2 3

77.8 3

3.4 62.0 69.2 51 3.6 57.0 62.2

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4.0 49.4 51.4 4

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.5 bb H/U ratio shall be confirmed equal or less than 0.45 prior shipment 3

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