ML19276G337
| ML19276G337 | |
| Person / Time | |
|---|---|
| Site: | 07106386 |
| Issue date: | 05/01/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19276G336 | List: |
| References | |
| NUDOCS 7905250346 | |
| Download: ML19276G337 (3) | |
Text
Form NR 431 8 U.S. NUCLEAR REGULATORY COMMISSION 33 CERTIFICATE OF COMPLIANCE g 7, For Radioactive Materials Packages 1.f a) Certificate Number 1.(b) Revision No.
1.(c) Package identification No.
1.fd) Pages No. 1.(e) Total No. Page 6386 4
USA /6386/AF 1
3
- 2. PREAMBLE 2.(a)
This certificate is issued to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the Department of Transportation Hazardot 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), as amended.
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.(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 er 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 Sutpart D of 10 CFR 71. as applicable, and the coralitions specit..!
in item 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class, other Condhions, 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 f10 pounds, empty.
The oblong cross section dimensions are approximately 35.5 inches high by 33.0 inches wide.
The con-tainer was originally designed to ship unirradiated fuel modules of the A1G/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, and rodded ASNPP fuel cells.
The [
loaded container maximum weight is 12,421 pounds.
(3) Drawings 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.
79052503f%
ese****V
Page 2 - Certificate No. 6386 - Revision No. 4 - 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 AlG reactor cell, rodded.
(xi) ASNPP fuel cell with control rod, and control rod holddown device installed.
(2) Maximum quantity of material per package (i) One fuel assembly as described in 5(b)(1)(i), 5(b)(1)(ii),
5(b)(1)(iii) or 5(b)(1)(xi).
l
9 Page 3 - Certificate fio. 6386 - Revision No. 4 - 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(D)(1)(vii), 5(b)(1)(viii), or 5(b)(1)(x).
(iii)
Four fuel assemblies as described in 5(b)(1)(ix).
III (c)
Fissile Class Maximum number of packages per shipment:
(1) For the contents described in 5(b)(1)(iii) and limited in 5(b)(2)(i):
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), and 5(b)(1)(xi) and limited in 5(b)(2)(i), 5(b)(2)(ii), and 4
5(b)(2)(iii):
6.
Expiration date:
February 28, 1983.
REFERENCES Safety Analysis Report for 235R001 Shipping Centainer, WAPD-0P(R)RD-357 dated August 11, 1970.
Supplements:
Knolls Atomic Power Laboratory letter AIG 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 October 30, 1970, Knolls Atomic Power Laboratory letters AlG 25-131' dated April 9,1971, and AlG 25-191; dated May 11, 1971, Bettis Atonic Power Laboratory letters WAPD-0P(R)C-94; dated May 16, 1972, WAPD-0P(R)C-199; dated December 13, 1972, and WAPD-0P(R)C-229; dated 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, 1973, G#6095; dated August 17,1978, and G#6208; dated March 8,1979.
l FOR THE U.S. NUCLEAR REGULATORY COMMISSION A
Ri Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety Dated: _
.