ML20248L326
| ML20248L326 | |
| Person / Time | |
|---|---|
| Site: | 07109184 |
| Issue date: | 03/09/1998 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20248L307 | List: |
| References | |
| NUDOCS 9803190346 | |
| Download: ML20248L326 (3) | |
Text
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CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES
- 1. a CERTInCATE NUMBER b. REVISION NUMBER
[ c PACKAGE IDENMMCATION NUMBER d PAGENUMBER e. TOTAL NUMBER PAGES W 9184 4 USA /9184/B(U) 1 2 l
- 2. PREAMBLE l
- a. 71us cem6 cme is issued to cemfy that the packaging and consents 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 Radmactive Matenal
- l b. This certincase does not reiseve the consignor frorn compliance with any requirement of the regulations of the U.s. Department of Transportation or c:her apphcable regulatory agencies, including the government of any counuy through or into which the package will be transported.
- 3. THIS CERT 1HCATE IS ISSUED ON THE B ASIS OF A $APETY ANALY$15 REPORT OF THE PACKAGE DESIGN OR APPUCATION
& !$$UED TO(Near eders2) b TITLE AND IDDmHCATION OF REPORT OR APPUCAT10N:
l p Packaging Technology, Inc. Nuclear Packaging, Inc. consolidated application p 4507 0 Pacific Highway East dated March 31, 1989, as supplemented.
p Tacoma, WA 98424-2633 p .. oOCxtr NuMnER 71-9184 4 CONDITIONS Tius cert 6cate is condsuonal upon fulfilhng the requirements of 10 CRt Part 71, as applicable, and the conditions specified below.
S.
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y (a) Packaging ll (1) Model No.: PAS-1 (2) Description li The packaging consists of a primary containment vessel (20.5" OD x 23.4" b)
OH) enclosed inside a secondary containment vessel and radiation shield 1 (32.5" OD x 39.0" OH). The 15 milliliter water sample is contained within
,I a undefined sample cask. Additionally, four iodine collection cartridges Ej and four offgas vials are maintained inside the foam shoring above the I'
I sample cask. Loose vermiculite surrounds the perimeter of the sample cask I to absorb the water sample should leakage occur. Completely surrounding the secondary containment vessel and radiation shield is a foam filled b
steel encased overpack (48.0" OD x 66.0" OH) which provides impact and thermal protection.
f 8 The primary containment vessel, which is constructed of 304 stainless bl steel varying in thickness from 3/4" to 1.25", is provided with double Wj Viton 0-ring seals and a sealed test port between the seals for leak bj testing. The assembly is secured with eight, 3/8"-16 UNC x 8" long screws.
I l
D} The secondary containment vessel and radiation shield provides 0.75" thick b steel and 5.1" thick lead shielding in the radial direction, 2.0" thick Blj steel and 5.1" thick lead shielding on the bottom, and 3.5" thick steel Dj and 4.8" thick lead shielding on the top. The lid is secured with eight,
, b 1.0"-8 UNC x 3.0 long bolts. The lid is sealed with two Viton 0-rings b with a sealed test port between the seals for leak testing.
Dj
>{ The overpack provides about 7.25" thick foam on the sides and about 13" on D the top and bottom. The two halves of the overpack are held together by
)b l
eight, 3/4"-10 UNC x 1.5" long bolts. A Necprene gasket prevents rain bj water from entering the overpack.
p
>f The weight of " package including a maximum sample cask weight of 1,375 b j pounds, is about 12,800 pounds, b4 9803190346 980309 PDR ADOCK 07109184
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w i NRC FORM SISA ODNDmONS trav=we U.S. NUCLEAR REGULATORY COtetAISSION k
j l Pag,e 2 - Certificate No. 9184 - Revision No. 4 - Docket No. 71-9184 ll i
5 5.(a)(3) Drawings I lj The package is constructed in accordance with Nuclear Packaging, Inc. L I
Drawing No. X-20-218D, Sheets I and 2, Rev. C. I I i 1 Contents 1
(b) I l
lj (1) Type and form of material I I
I M (1) Radioactive material in form of liquid or gaseous samples in sample I I casks, cartridges and vials. I l !
9{ (ii) Byproduct and activation materials as solids and process solids or l l l;
j resins, either dewatered, solid, or solidified in secondary I 1 containers. l l Jl l J{ (2) Maximum quantity of material per package [
J l i 1 50 Ci of mixed fission and activation products, 15 milliliters of liquid, I I 1 one sample cask or secondary container and four cartridges and four vials. I l
3; l !
1l 6. In addition to the requirements of Subpart G of 10 CFR Part 71, each package i prior to first use must meet the acceptance tests and criteria specified in [
Section 8.1, must be maintained in accordance with Section 8.2, and must be 3]I
) prepared for shipment in accordance with Chapter 7.0 of the application, and the I
[
supplement dated July 8,1994. '
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/ 7. The package authorized by this certificate is hereby approved for use under the [
/ general license provisions of 10 CFR 671.12.
- 8. Expiration date: July 31, 1999. f REFERENCES
[
Nuclear Packaging, Inc., consolidated application dated March 31, 1989. f Supplement dated: April 7, 1989.
[
VECTRA Technologies, lac., supplements dated: July 8,1994 and January 30, 1998.
Transnuclear, Inc., supplement dated January 30, 1998.
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FOR THE U.S. NUCLEAR REGULATORY COMMISSION l I I Cass R. Chappe11bhief
: h , I I
j
)f Package Certification Section Spent Fuel Project Office i
)i Office of Nuclear Material Safety and Safeguards
[
Date: March 9, 1998 l-f> -
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,s ~g% UNITED STATES e g j NUCLEAR REGULATORY COMMISSION WASNINGTON, D.C. aasas aaat l
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\*****/ APPROVAL RECORD Model No. PAS-1 Certificate of Compliance No. 9184 !
Revision No. 4 By letters dated January 30, 1998, VECTRA Technologies, Inc., and Transnuclear, Inc. requested that the certificate holder for Certificate of l Comsliance No. 9184 for the Model No. PAS-1 package be changed from VECTRA i Technologies, Inc., to Packaging Technology, Inc. Packaging Technology, Inc.,
has accepted responsibility for the completeness and accuracy of the statements and representations of the previous certificate holder. Packaging Technology, Inc., will be responsible for maintenance of the certificate, the safety analysis report for the package design, and the quality assurance records in accordance with 10 CFR 571.91(c). Packaging Technology, Inc., has been issued Quality Assurance Program Approval for Radioactive Materials Packages No. 0678, under Subpart H of 10 CFR Part 71.
The Certificate has been revised to show Packaging Technology, Inc., as certificate holder. These changes do not affect the ability of the package to l meet the requirements of 10 CFR Part 71. l 1
M Cass R. Chappell, Chief 1 Package Certification Section !
Spent Fuel Project Office l Office of Nuclear Material i Safety and Safeguards !
Date: March 9, 1998
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