ML18152A984
| ML18152A984 | |
| Person / Time | |
|---|---|
| Site: | 07106386 |
| Issue date: | 05/31/2018 |
| From: | John Mckirgan Spent Fuel Licensing Branch |
| To: | Pratt R US Dept of the Navy |
| White B | |
| Shared Package | |
| ML18152A982 | List: |
| References | |
| EPID L-2017-LLA-0062, USA/6386/B(U)F-96 | |
| Download: ML18152A984 (3) | |
Text
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 6386 22 71-6386 USA/6386/B(U)F-96 1 OF 3
- 2. PREAMBLE
- a. This certificate is issued to certify that the package (packaging and contents) described in Item 5 below meets the applicable safety standards set forth in Title 10, Code of Federal Regulations, Part 71, Packaging and Transportation of Radioactive Material.
- b. 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
- a. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION U.S. Department of Energy Safety Analysis Report for 235R001 Shipping Container Division of Naval Reactors dated August 11, 1970, as supplemented.
Washington, DC 20585
- 4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.
5.
(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 standard size or partial S8G fuel modules by use of a special frame assembly and cradle clamps, rodded or unrodded D2W fuel cells, rodded S9G fuel cells and rodded A1B fuel cells. The loaded container maximum weight is 17,200 pounds.
(3) Drawings The packaging is constructed in accordance with Container Research Corporation Drawing No. 235R001, Rev. BC, and Bettis Atomic Power Laboratory Drawing No. 6292E98, Rev. B.
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 6386 22 71-6386 USA/6386/B(U)F-96 2 OF 3 5.(b) Contents (1) Type and form of material Unirradiated fuel assemblies of the following types:
(i) A1G reactor cell without upper mechanism and with control rod, leadscrew and shipping fixture installed on rodded type modules.
(ii) Standard size S8G reactor cluster with regular or substitute support adapters and regular control rods. If only one cell is shipped per container, a dummy load shall be installed for balance.
(iii) Partial size S8G reactor cluster with regular or substitute support adapters and regular control rods. If only one cell is shipped per container, a dummy load shall be installed for balance.
(iv) D2W side or central fuel cell and shear block with control rod inserted in rodded fuel cell.
(v) D2W corner fuel cell, with shear block, unrodded.
(vi) S9G type fuel cell with control rod inserted.
(vii) A1B type fuel cell with control rod inserted.
(2) Maximum quantity of material per package (i) One fuel assembly as described in 5(b)(1)(i), 5(b)(1)(iv), 5(b)(1)(v), 5(b)(1)(vi) or 5(b)(1)(vii),
(ii) Two fuel assemblies as described in 5(b)(1)(ii) or 5(b)(1)(iii).
5.(c) Criticality Safety Index (1) For contents described in 5.(b)(1)(ii), 5.(b)(1)(iii), and limited in 5.(b)(2)(ii): 25.0 (2) For contents described in 5.(b)(1)(i), 5(b)(1)(vi), 5(b)(1)(vii),
and limited in 5(b)(2)(i) : 100.0 (3) For contents described in 5.(b)(1)(iv), and 5.(b)(1)(v), and limited in 5.(b)(2)(i): Reserved
- 6. The contents as described in 5.(b)(1)(i) through 5.(b)(1)(v) and limited in 5.(b)(2) shall be designated as B(U)F.
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 6386 22 71-6386 USA/6386/B(U)F-96 3 OF 3
- 7. Transport by air of fissile material is not authorized.
- 8. Expiration date: April 30, 2020.
REFERENCES Safety Analysis Report for 235R001 Shipping Container, WAPD-OP(R)RD-357 dated August 11, 1970.
Supplements: Knolls Atomic Power Laboratory letter A1G 25-159, dated October 2, 1970. Bettis Atomic Power Laboratory letters WAPD-0P(R)RD-444, dated October 9, 1970; WAPD-OP(R)RD-476, dated October 26, 1970; and WAPD-OP(R)RD-488, dated October 30, 1970. Knolls Atomic Power Laboratory letters AlG 25-181, dated April 9, 1971; and A1G 25-191, dated May 11, 1971. Bettis Atomic Power Laboratory letters WAPD-OP(R)C-94, dated May 16, 1972; WAPD-OP(R)C-199, dated December 13, 1972; and WAPD-OP(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, 1978; G#6095, dated August 17, 1978; G#6208, dated March 8, 1979; G#6373, dated September 4, 1979; G#68l3, dated October 17, 1980; G#C85-0467, dated July 17, 1985; G#C88-8112, dated October 18, 1988; G#90-03655, dated August 10, 1990; G#92-03560, dated June 15, 1992; G#96-03371, dated March 15, 1996, G#C97-03444 dated April 8, 1997; G#C99-03514, dated June 1, 1999; G#C99-03688, dated December 30, 1999; G#C02-0750, dated April 8, 2002; G#C03-00273, dated January 24, 2003; G#C03-01695, dated July 14, 2003; G#C07-02462, dated December 18, 2007; G#09-02803, dated June 11, 2009; G#09-04797, dated November 20, 2009; G#C10-00794, dated March 31, 2010; G#C10-03819, dated September 30, 2010; G#14-04645, dated October 7, 2014 ; G#C17-02402, dated June 9, 2017.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
/RA/
John McKirgan, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Date: 5/31/18