ML19253D070
| ML19253D070 | |
| Person / Time | |
|---|---|
| Site: | 07106386 |
| Issue date: | 12/03/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19253D067 | List: |
| References | |
| NUDOCS 7912120571 | |
| Download: ML19253D070 (3) | |
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Form NRC418 U.S. NUCLEAR REGULATORY COMMISSION U
CERTIFICATE OF COMPLIANCE 10 C R 71 For Radioactive Materials Packages 1.fa) Certificate Number 1.(b) Revision No.
1.(c) Packa e Identification No.
1.(d) Pages No. 1.(e) Total No. Pages 6386 5
JSA/6386/AF.
1 3
- 2. PRE AMBLE 2.(a)
This certificate is issued to satisfy Sections 173.393a,173.394, '73.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Ses.tions 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packaging and contents described in item S 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.fc)
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:
U.S. Department of Energy Safety Analysis Report for 235R001 Division of Naval Reactors Shipping Container dated August 11, 1970, Washington, DC 20545 as supplemented.
3.(c)
Docket No. 71-6386
- 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 S below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a)
Packaging (1) Model No.: 235R001 (2) Description The 235R001 shipping container structure is horizontal, having an oblong cross section and is fabricated from 0.104 inch thick carbon sheet steel.
The container is 313 inches long and has a maximum weight of 4,640 pounds, empty. The oblong cross section dimensions are approximately 35.5 inches high by 33.0 inches wide. The container was originally designed to ship unirradiated fuel modules of the AlG/A4W type.
Subsequently, the container has been adapted to ship AlW-3 fuel modules using a strongback, partial AlW-R3 fuel modules using module support assemblies, standard size or partial S8G fuel modules by use of a special frame assembly and cradle clamps, S3G-3 refueling modules using cell support assemblies, rodded or unrodded DlG fuel modules, rodded ASNPP fuel cells and rodded or unrodded 02W fuel cells.
The loaded container maximum weight is 12,421 pounds.
l (3) Drawings 1541 301 The packaging is constructed in accordance with Container Research Corporation Drawings Nos. 235R001, Rev. C, 235R004, Rev. C, and 235R005, Rev. O, and Westinghouse Electric Corporation Drawings Nos. 973D425, Rev. 1, 903E693, Rev. 3, Sheet 1, 2 and 3 of 3, and 947J076, Rev. O.
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Page 2 - Certificate No. 6386 - Revision No. 5 - Docket No. 71-6386 (b) Contents (1) Type and form of material Unirradiated fuel assemblies of the following type, (i) AlG and A4W reactor cell without upper mechanism and with control rod, leadscrew and shipping fixture installed on rodded type modules.
(ii) A4W Reactor Test Assembly (RTA).
(iii) AlW-3 module without upper mechanism and with control rod, leadscrew, and control rod holddown device installed on rodded type modules.
(iv) AlW-R3 Partial Lower Module.
(v) Standard size S8G reactor cluster with regular or substitute support adapters and regular control rods or Boral poison rods with control rod holddown devices installed.
If only one cell is shipped per container, a dummy load shall be installed for balance.
(vi) Partial size S8G reactor cluster with regular or substitute support adapters and regular control rods or Boral poison rods with control rod holddown devices installed.
If only one cell is shipped per container, a dummy load shall be installed for balance.
(vii) S3G-3 refueling cells, with a maximum of one first pass 0-1 reactor cell assembly per container.
(viii)
DlG fuel module, rodded.
(ix)
DlG removable fuel assembly (RFA), unrodded.
(x) AlG fuel cluster, fueled end only of full A1G reactor cell, rodded.
(xi) ASNPP fuel cell with control rod, and control rod holddown device installed.
(xii)
D2W new side or central fuel cells with control rod and control rod holddown device, or'D2W new cornar fuel cells, unrodded.
(2) Maximum quantity of material per package (i) One fuel assembly as described in 5(b)(1)(1), 5(b)(1)(ii),
5(b)(1)(iii) or 5(b)(1)(xi).
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Page 3 - Certificate No. 6386 - Revision No. 5 - Docket No. 71-6386 (2) Maximum quantity of material per package (Cont'd.)
(ii)
Two fuel assemblies as described in 5(b)(1)(iv), 5(b)(1)(v),
5(b) 1)(vi), 5(b)(1)(vii), 5(b)(1)(viii), 5(b)(1)(x) or 5(b)1)(xii).
(iii)
Four fuel assemblies as described in 5(b)(1)(ix).
(c) Fissile Class III Maximum number of packages per shipment:
(1) For the contents described in 5(b)(1)(iii) and limited in 5(b)(2)(1):
18 (2) For the contents described in 5(b)(1)(i), 5(b)(1)(ii), 5(b)(1)(iv),
5(b)(1)(v), 5(b)(1)(vi), 5(b)(1)(vii), 5(b)(1)(viii), 5(b)(1)(ix),
5(b)(1)(x), 5(b)(1)(xi), and 5(b)(1)(xii) and limited in 5(b)(2)(i),
5(b)(2)(ii), and 5(b)(2)(iii):
4 6.
Expiration date:
February 28, 1983.
REFERENCES Sa#ety Analysis Report for 235R001 Shipping Container, WAPD-0P(R)RD-357 dated August 11, 1970.
Supplements:
Knolls Atomic Power Laboratory letter AlG 25-159; dated October 2, 1970, Bettis Atomic Power Laboratory letters WAPD-0P(R)RD-444; dated October 9, 1970, WAPD-0P(R)RD-476; dated October 26, 1970, and WAPD-0P(R)RD-488; dated 30, 1970, Knolls Atomic Power Laboratory letters AlG 25-181; dated April 9.1971, and AlG 25-191; dated May 11, 1971, Bettis Atomic Power Laboratory letters WAPD-OP(R)C-94; dated May 16,1972, WAPD-0P(R)C-199; dated December 13, 1972, and WAPD-0P(R)C-229; daud March 6,1973, Naval Reactors letters G#5078; dated January 26,1976, G#5776; dated September 8,1977, G#5905; dated January 23, 1978, G#5923; dated February 22, 1978, G#6095; dated August 17, 1978, G#6208; dated March 8,1979, and G#6373; dated Septaaber 4,1979.
l FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and gg Material Safety Dated:
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