ML20147F890
| ML20147F890 | |
| Person / Time | |
|---|---|
| Site: | 07109932 |
| Issue date: | 03/19/1997 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20147F887 | List: |
| References | |
| NUDOCS 9703270262 | |
| Download: ML20147F890 (2) | |
Text
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gwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwww.ww p NRC FbRM 618 U.S. NUCLEAR REIULATORY COMMISSION N
m CERTIFICATE OF COMPLIANCE
, e cm n FOR RADIOACTIVE MATERIALS PACKAGES U
h 1,s CERTIFICATE NUMP.ER I
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- b. REVISION NUMBER c PACKAGE IDENTIFICATION NUMBER
- d. PAGE NUMBER c. TOTAL Nt'MBER PAGES g
N 9932 4
USA /9932/Bf )
1 2
U N
- 2. PREAMBLE N
- a. This cenificate is issued to cenify that the packaging and cone 'ts described in Item $ below, meets the applicable safety standards set fonh in Title 10.
U Code of Federal Regulations, Pan 71," Packaging and Transporation of Radioactive Material."
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- b. This cenificate does not uheve the consignor from compliance with any requirement of the regulations of the U.S. Depanment of Transponation or other N
applicable regulatory agencies, including the government of any country through or into which the package will be transponed.
N N
3 THIS CERTIRCATE IS ISSUED ON THE B ASIS OF A S AFETY AN ALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION q
l a ISSUED TO(Naw and Adderss)
- b. TITLE ANDIDENTinCATION OF REPORTOR APPLICATION:
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Bj d
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- l U.S. Department of Energy Safety Analysis Report on Model UC-609 Shipping I
l Washington, DC 20585 Package, Report No. UCRL-52424, August 1977, d
I as supplemented N
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- c. DOCKET NUMBER 71-9932
( CONDITIONS g
This certificate is conditional upon fulfilhng the requirements of 10 CFR Pan 71, as applicable, and the conditions specified below.
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5.
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q B
(a)
Packaging I
B N
W (1)
Model No.: UC-609 I
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(2)
Description I
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b Packaging for large quantities of tritium. The containment vessel is a
b 1/8-inch thick 316 stainless steel, 18-inches in diameter by 44 inches a
B long. An aluminum tube forms a 10-inch diameter by 31-inch long g
b containment cavity. The space between the stainless steel outer shell a
p and the aluminum tube is filled with aluminum honeycomb.
Access to the g
i containment cavity is through a 10-inch diameter opening at one end.
g g
Positive closure of the flanged stainless steel cover plate is g
b accomplished using eight (8), 3/8-inch alloy steel ~ bolts. The cover g
b closure is sealed with an inner copper gasket and outer Viton 0-ring g
p seal. A valved port between these gaskets is provided for leak testing.
g p
A manifold containing a valve and 200 psig pressure gage is welded to the g
g center of the cover plate. The containment vessel is centered and g
p supported within a 16-gauge steel drum 25 inches in diameter by 54-1/2 g
g inches high using Celotex insulation. The package gross weight is 500 g
p pounds.
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(3)
Drawings g
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The packaging is constructed in accordance with Lawrence Livermore g
Laboratory Drawing Nos.: AAA76-109771-0C, AAA75-ll3967-0B,
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g AAA75-113083-0A, AAA77-102165-00, AAA75-112930-0A, AAA77-104161-00, p
AAA77-104165-0A and AAA77-104163-0B.
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i Page 2 - Certificate No. 9932 - Revision No. 4 - Docket No. 71-9932 d,1 W
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(b)
Contents d
4 a
B.
(1)
Type and form of material e
B W
p Tritium in any form held within secondary containers.
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d p
(2)
Maximum quantity of material per package q
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p Decay heat not to exceed 48 watts.
Not more than 25 gm-moles (150 grams) g 3
of tritium, g
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i p
6.
The initial pressure within the containment vessel and secondary containers g
p shall be such that if all gases were released from the secondary containers the g
i I
maximum pressure within the containment vessel, at 20*C (68 F) would not g
i p
p exceed:
g q
s (a) 84 psig when no water is present, or g
B d
i p
(b) 45 psig when water is present.
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7.
The weight of the secondary containers shall not exceed a total of 120 pounds.
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Acceptance tests and maintenance shall be in accordance with Section 8.0 of l
g Lawrence Livermore Laboratory Report No. UCRL-52424, August 1977.
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9.
Operating procedures equivalent to those specified in Section 7.0 of Lawrence l
)
y Livermore Laboratory Report No. UCRL-52424, August 1977, shall be established for use, g
9 g
N 10.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 671.12.
l g.
l 11.
Expiration date: March 31, 2002.
l
!j, REFERENCES E
s a
5{
Lawrence Livermore Laboratory Report No. UCRL-52424, August 1977.
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d 5
DOE Supplement dated: October 30, 1995.
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FOR THE U.S. NUCLEAR REGULATORY COMMISSION N
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D Cass C. Chappell, Chief Ul i
Bj Package Certification Section 4
b Spent Fuel Project Office E
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Office of Nuclear Material Safety Ul B;
and Safeguards Wl l
l Dl N '
W E
Dj Date:
03/19/97 N
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'r WASHINGTON, D.C. 308s6 0001
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APPROVAL RECORD Model No. UC-609 Certificate of Compliance No. 9932 Revision No. 4 By application dated October 25, 1995, the Department of Energy requested renewal of Certificate of Compliance No. 9932. The application also included changes to the package.
The changes to the package will be considered as a separate amendment.
The Certificate of Compliance has been renewed for a five-year term which expires on March 31, 2002.
a.44 L M!A-
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Cass R. Chappel, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards 03/19/97 Date:
,