ML20133P684
| ML20133P684 | |
| Person / Time | |
|---|---|
| Site: | 07109071 |
| Issue date: | 01/17/1997 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20133P669 | List: |
| References | |
| NUDOCS 9701270058 | |
| Download: ML20133P684 (4) | |
Text
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U.S. NUCLEAR REIULATORY COMMISSION g 4 GSeh CERTIFICATE OF COMPLIANCE
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FOR RADIOACTIVE MATERIALS PACKAGES U l
p T a. CERnRCATE NUMBER b. REVISION NUMBER c. PACKAGE IDENTlHCATION NUMBER d. PAGE NUMBER e. TOTAL NUMBER PAGES 9071 6 USA /9071/B( ) 1 3 g
- 2. PREAMBLE N
$ N
- a. This certificate is issued to certify that the packaging and contents described in item $ below, rnects the applicable safety standard set forth in Title 10.
N 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 Tran;portation or other 1 N applicable regulatory agencies, including the government of any country through or into which the package will be transported. E
- 3. Ulls CERTinCATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICARON
! a.15 SUED TO(Name sad A&treu) b. TITLE AND IDENTIFICARON OF REPORT OR APPLICAT10N-N d p ANEFCO, Incorporated ANEFC0 application received June 14, 1976, g i
g P.O. Box 171 with report, " Safety Analysis Report Cask g g Moodus, CT 06469 AP-101," as supplemented. g B
d p c. DOCxET NUMBER 71-9071 g g 4. CONDITIONS g
) This certificate is conditional upon fulfil;ing the requirements of 10 CFR Part 71, as applicable, and the conditions specified below. g j $ 5-l l (a) Packaging l
l (1) Model No.: AP-101 l
l (2) Description - N I
E A steel encased, lead shielded cask for non-fissile radioactive material. U
' 5 The overall dimensions of the cask are 40 inches in diameter by 193 inches N I
long. The cask consists of two concentric stainless steel cylindrical I N
8 shells. The inner shell-is 5/8-inch thick by 28-inch ID; the outer N 8
stainless steel shell is 1-1/2-inch thick by 39-1/4-inch OD and a 3-1/2-inch N poured lead shield fills the space.between. The outer shell is surrounded E E
by a 0.140-inch thick stainless steel thermal shield separated by a a i 8 0.125-inch thick stainless steel spacer wire. The cavity is 28 inches in d B
diameter by 167 inches long. The base is a welded stainless steel d N construction with 3 inches of poured lead. The flanged lid is of stainless a 8 steel and lead. Closure is provided by twenty,1-1/2-inch diameter bolts and d N a gask-o-seal closure seal . There are two penetrations into the containment U B vessel for drain lines which are plugged and gasketed with a neoprene seal. d D The cask is equipped with removable, canned balsa impact limiters at each I b end. The overall dimensions of the cask with impact limiters in place are a b 84 inches in diameter by 236 inches long. The cask has four lifting d
- trunnions, two redundant pairs for lifting. Three of the trunnions are used d B for tie-down of the cask for shipment. The package gross weight is d N approximately 62,000 pounds. E R d
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>l r D j i b; 5. (a) Packaging (Continued) r ;
- i !
Bj Bj (3) Drawings L l Bj E 1 fj The packaging is fabricated in accordance with ANEFCO, Incorporated i ;
b; Drawing Nos. SC-101, Rev. A; SC-102; SC-103, Rev. A; SC-104, Rev. B; I E SC-107, Rev. A; SC-108; SC-110, Rev. A; and SC-111. L l r
B p (b) Contents i 1 9 L ,
i B (1) Type and form of material r l B r l p Greater than Type A quantity of byproduct material in the form of dry, r p solid, metallic waste material and activated reactor components. r ,
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p (2) Maximum quantity of material per package t ;
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p Weight of contents not to exceed 10,000 pounds. Internal decay heat of i i p contents not to exceed 300 watts. i l 9 L l B
- 6. The package must be shipped dry. In preparation for shipment, the cask cavity g al must be drained of all excess water. A vacuum pump must be used to reduce the i il cavity pressure below the vapor pressure corresponding to the measured g a temperature of the drained water. The cavity pressure must be held below the t i vapor pressure determined for at least 90 minutes. A dry loaded package need not i i be vacuum dried provided the " empty" cask cavity and drain lines are verified not g jl to contain liquid prior to each loading. t
- 7. Except for close fitting contents, appropriate shoring must be used in the cask f g cavity to limit movement of the contents during accident conditions of transport. t l 8. In addition to the requirements of Subpart G of 10 CFR Part 71:
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! a. The package must be operated and maintained in accordance with procedures in
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supplement dated December 12, 1991.
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- b. Prior to each shipment the gask-o-seal closure seal must be inspected. The '
!. gask-o-seal closure seal and the cavity drain 0-ring seals must be replaced
? with new seals within the 12-month period prior to shipment, or earlier if I inspection shows any defect. I E
- c. The package must be leak tested prior to each shipment in accordance with I operating procedures in supplement dated December 12, 1991. I l
N 9. The package authorized by this certificate is hereby approved for use under the 1 general license provisions of 10 CFR 671.12. '.,
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- 10. Expiration date: January 31, 2002. I l l o
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Page 3 - Certificate No. 9071 - Revision No. 6 - Docket No. 71-9071 E B
E B d B REFERENCES I B d 8
B ANEFCO, Incorporated Safety Analysis Report Cask AP-101, received June 14, 1976.
6 B d i B Supplements dated: July 21, August 6, and October 21, 1976; April 2 and 4 B September 12, 1986; September 26 and December 12, 1991; and November 25, 1996. 6 B; 6 B E I
B FOR THE U.S. NUCLEAR REGULATORY COMMISSION d B d W
D Cass R. Chappell, Chief g 3 Package Certification Section g B Spent Fuel Project Office g B Office of Nuclear Material g B Safety and Safeguards g .
! U l Date: 01/17/97 B 8 :
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APPROVAL RECORD Model No. AP-101 Package l Certificate of Compliance No. 9071 )
Revision No. 6 By application dated November 25, 1996, ANEFCO, Inc requested renewal of Certificate of Compliance No. 9071, for the Model No. AP-101 package. No changes in the package design or contents were requested. The applicant stated that the operating procedures, acceptance tests, and maintenance program had been reviewed, and were found to be complete and current.
The certificate has been renewed for a five year period which expires January 31, 2002.
$44 Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date 01/17/97 l
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