ML19249E596
| ML19249E596 | |
| Person / Time | |
|---|---|
| Site: | 07105894 |
| Issue date: | 09/05/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19249E595 | List: |
| References | |
| NUDOCS 7910020025 | |
| Download: ML19249E596 (3) | |
Text
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Form NRC418 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE 10 CFP 71 For Radioactive Materials Packages 1.la) Certificate Nurnt. '
f.(b) Revision No.
1.fc) Package Identification No.
1 (d) Pages No. 1.(e) Total No. Pages l
5894 1
USA /5894/AF 1
3
- 2. PRE AMBLE 2.(a)
This certificate is issued to satisfy Sections 173.393a.173.394.173.395. and 173.39G of the Department of Transportation Hazardous Materials Reoulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulathns (46 CFR 146 -149), as amerJod.
2.(b)
The packaging and contents described in item S below, meets the safety standards set forth in Subpart C of Titre 10, Code of Federal Regulations, Part *.1, " Packaging of Radioactive Materials for Transport and Transportaticn of Radioactive Material Under Certain Conditions.
2.fc)
This certificate does not relieve the consignor frorn compliance with any requirement of the regulations of the U.S. Department of Transportation or other acol. cable regulatory agenci+s, inc!uding 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 apotication:
U.S. Department of Energy Safety Analysis Report for 2.7 New Fuel Division of Naval Reactors Shipping Container dated July 15, 1968, Washington, D.C.
20545 as supplemented.
3.(c)
Docket No.
71-5894 4 CCNOITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart O M 10 CFR 71, as applicable, and the conditions specified in item 5 below.
-- - -Is Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a) Dackaging (1) Model No.: 2.7 New Fuel (2) Description The Model 2.7 New Fuel container was designed to ship and store new and unirradiated S5W Core R2 fuel modules. Adapters are used to permit additional shipments of S5W Core R3, AlW Core R2, and SIC Type I fuel modules.
The container assembly consists of two major components, an inner container which holds the fuel module and an outer container which supports the inner container.
The steel outer antainer is approximate 1" 24.5 inches wide by 24.5 inches high a 128 inches long.
The cross section of the outer container is octagnal, the steel shell ':hickness is 0.1875 inch, ASTM-A283 Gr. B.
The outer shell is st rrounded by a framework of steel stiffeners and rails.
The inner container is constructed from Type 304 CRES plates, 0.18/5 inch thick and is 7.76 inches square and 99 inches long. Bolted closure is provided for each container.
The gross weight of the package ranges frcm approximately 1500 tn 2000 pounds.
1062 i'7 7 01002 0C s
Page 2 - Certificate No. 5894 - Revision 1 - Docket No. 71-5894 (3) Drawings The packaging is constructed in accordance with Westinghouse Electric Corporation Drawing No. 924J152, Rev. 16.
(b) Contents (1) Type and form of material Unirradiated fuel assemblies of the following type, (i) SSW Core R2 standard module or corner module (ii) SSW Core R3 standard module or corner module (iii) AlW Core R2 standard cluster or half cluster (iv) SIC Core Type I standard cluster (v) S1C Core Type I fuel subassembly (vi) S5W Core 2 standard module or corner module (vii) AlW Core R2 subassembly (2) Maximum quantity of material per package (i) One fuel assembly as described in 5(b)(1)(i), 5(b C ii),
5(b)(1)(iii), 5(b)(1)(iv) or 5(b)(1)(vi).
l (ii) Two fuel assemblies as described in 5(b)(1)(v).
(iii) Four fuel assemblies as described in 5(b)(1)(vii).
l (c) Fissile Class III Maximum number of packages per shipment:
(1) For the contents described in 5(b)(1)(i),
No more than 5(b)(1)(ii), 5(b)(1)(iv), 5(b)(1)(v), and 5(b)(1)(vi) one total core's j
and limited in 5(b)(2)(i) and 5(b)(2)(ii):
worth (2) For the contents described in 5(b)(1)(iii) and 25 total, with the 5(b)(1)(vii) and limited in 5(b)(2)(i) and number of packages 5(b)(2)(iii):
as described in 5(b)(1)(vii) and limited'in 5(b)(2)(iii) not to exceed four 1 C 5 2 l 'I
6.
Exp - tion date:
February,28, 1983 i
Page 3 - Certificate No. 5894 - Revision 1 - Docket No. 71-5894 REFERENCES Safety Analysis Report for 2.7 New Fuel Shipping Container, WAPD-0P(R)S-2650 dated July 15, 1968.
Supplements:
Bettis Atomic Power Laboratory letters WAPD-0P(R)S-2800 dated September 3, 1968 and WAPD-0P(R)S-3425 dated August 14, 1969, and Department of Energy letter G# 6291 dated July 13, 1979.
FOR THE U.S. IUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety SEP 0 51979 Date:
s W
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