ML20024B409
| ML20024B409 | |
| Person / Time | |
|---|---|
| Site: | 07106406 |
| Issue date: | 06/23/1983 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20024B406 | List: |
| References | |
| NUDOCS 8307080669 | |
| Download: ML20024B409 (5) | |
Text
Form NRC.618 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE 10 CFR 71 For Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.(e) Total No, Pages 6406 3
USA /6406/AF 1
4
- 2. PREAMBLE 2.(a)
This certificais is issued to satisfy Sections 173.393a,173.394,173.395, and 173.39G of the Department of Transportation Hazard 3us Materials Regulations (49 CFR 170189 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 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 Matenel 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 or application:
U.S. Department of Energy U.S. Energy Research and Development Division of Naval Reactors Administration Application dated Washington, DC 20545 July 19, 1977, as supplemented.
3.(c)
Docket No. 7)-6406 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 Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a)
Packaging (1) Model No.:
None specified (2)
Description Specific packaging is not required.
Safety is independent of packaging.
(b) Contents (1) Type and form of material Unirradiated fuel assemblies of the following types:
(i) S5G Fuel Experiment Assembly (FEA) in the FEA shipping container.
(ii)
S5G Double Fuel Experiment Assembly (DFEA) in the DFEA shipping container.
(iii)
A1W-3 Removable Uninstrumented Subassembly (RUS) in the flodel 25.0 shipping container.
(iv) AlW-3 Prototype "A" Module or A1W-3 Shipboard "A" tiodule in the Model 2.7/3.6 shipping container.
i 8307080669 830623 PDR ADOCK 07106406 C
l Page 2 - Certificate No. 6406 - Revision No. 3 - Docket No. 71-6406 l
(b) Contents (Continued)
(v) Rodded instrumented SIC fuel module in the Model 7481E12 shipping container.
(vi) SlC fuel module or SlC peripheral assembly in the SlC bird cage shipping container.
(vii)
S1W-3 Removable Subassembly (RSA) in the SlW RSA/ Metal Box.
(viii)
S5W-2 Removable Subassembly (RSA) in the S5U RSA/ Bird Cage.
(ix) S5W-R2/R3 or S5W-2 module in the S5W New Module Container.
(x) AlW-2/R2 cluster or half cluster in the Model 658C shipping container.
(xi) S3G-2A/2B fuel module in the Model 7481E12 or Model 9SK218 shipping container.
(xii) D2W rodded fuel cell or unrodded corner type D2W fuel module in a model 658H1 AB shipping and storage container. Rodded type fuel module shall have a control rod and control rod holddown device installed.
(xiii)
S7G unit cell or reactor cell assembly in a model 658ElAB shipping and storage container, with shipping clamp installed.
(xiv)
Advanced Test Core (ATC) welded fuel cluster or ATC cage assembly fuel cluster in a model 660Bl/660Cl container.
(xv)
DlG fuel module in a model 572Al or 572B1 shipping container and DlG Removable Fuel Assembly (RFA) in a Model 573Al or 573B1 shipping container. A control rod and control rod holddown device need not be installed in the DlG fuel module.
(xvi)
DIG Removable Fuel Assembly (RFA) in a model 573Al or 573B1 shipping container.
(xvii)
PWR Core 1 (Seed 2, 3 or 4) unrodded seed fuel assembly or PWR i
Core 2 (Seed 1 or 2) unrodded seed fuel assembly, in unspecified shipping containers.
(xviii)
PWR Core 1 (Seed 2, 3 or 4) unrodded seed fuel subassembly or PWR Core 2 (Seed 1 or 2) unrodded seed fuel subassembly, in unspecified shipping containers.
(xix)
S8G rodded fuel cell in unspecified shipping container with control rod holddown device installed.
(xx)
S5G type unit cell in a 658El AB shipping container.
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Page 3 - Certificate No. 6406 - Revision No. 3 - Docket No. 71-6406 (xxi) AlW-3 Prototype Peripheral Subassably or Alu-3 Prototype Center Subassembly in the Model 2.7/3.6 shipping container.
(2) flaximum quantity of material per package (i)
One fuel assembi as described in 5(b)(1)(i), 5(b)(1)(ii),
5(b)(1)(iii),5()(1)(iv),5(b)(1)(v),5(b)(1) 5(b)(1)(vii), 5( )(1)(viii), 5(b)(1)(ix), 5(b)(vi),.
(1)(x),
5(b)(1)(xi), 5(b)(1)(xii), 5(b)(1)(xiii), 5(b)(1)(xiv),
{
5(b)(1)(xvi), 5(b)(1)(xvii), 5(b)(1)(xviii), 5(b)(1)(xix) or 5(b)(1)(xx).
l (ii) Two fuel assemblies as described in 5(b)(1)(xv).
(iii) Three fuel assemblies as described in 5(b)(1)(xxi).
(c)
Fissile Class III l
Maximum number of packages per shipment:
(1)
For the contents described in 5(b)(1)(fi),5(b)(1)(iv),5(b)(1)(vi),5(b)(1)(xi),
l 5(b)(1)(xii),5(b)(1)(xiii),5(b)(1)(xiv),5(b)(1)(xv),
l 5(b)(1)(xvii), 5(b)(1)(xix), 5(b)(1)(xx) or 5(b)(1)(xxi) l and limited in 5(b)(2)(1), 5(b)(2)(ii) and 5(b)(2)(iii) 1 (one)
(2)
For the contents described in 5(b)(1)(iii), 5(b)(1)(v), 5(b)(1)(ix),' 5(b)(1)(x) or 5(b)(1)(xviii) and limited in 5(b)(2)(1).
2 (two)
(3)
For the contents described in 5(b)(1)(i) and 5(b)(1)(viii) and limited in 5(b)(2)(i).
3 (three)
(4) For the contents described in 5(b)(1)(vii) and limited in 5(b)(2)(1).
4 (four)
(5) For the contents described in 5(b)(1)(xvi) and limited in 5(b)(2)(i).
8 (eight) 6.
Commingling of packages for Fissile Class III shipment is authorized provided that the sum of-the ratios of the number of packages of an individual type to be shipped to the maximum allowable number of packages of that type per shipment does not exceed unity.
7.
Expiration date: June 30, 1988.
6 Page 4 - Certificate No. 6406 - Revision No. 3 - Docket No. 71-6406 REFERENCES U.S. Energy Research and Development Administration application dated July 19, 1977.
Supplements:
Department of Energy letters G#5868; dated January 4, 1978, with enclosures, and G #6291; dated July 13, 1979.
FOR THE V.S. NUCLEAR REGULATORY COMMISSION Charles E. il cDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
1 4
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U.S. Nuclear Regulatory Commission Transportation Certification Branch Approval Record Model No. flone Specified Docket flo. 71-6406 By application dated July 27, 1982, U.S. Department of Energy requested renewal of Certificate of Compliance No. 6406.
No changes have been authorized to the package design since approval of latest supplement dated July 13, 1979.
The staff concludes that the statements of the original application, as supplemented, satisfies the requirement for renewal of the Certificate of Compliance.
Charles E. F acDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date:. 3 2 3 1S83
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