ML20206F488

From kanterella
Jump to navigation Jump to search
Certificate of Compliance 9181,Rev 3,for Models PAS-2 & PAS-2A.Approval Record Encl
ML20206F488
Person / Time
Site: 07109181
Issue date: 06/17/1986
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20206F472 List:
References
NUDOCS 8606240484
Download: ML20206F488 (3)
v • d • e


Text

r------------------------------------------------------ii I macroni m U.S. NUCLEAR CE2ULATORY C3MMISSl!N I

  • asi CERTIFICATE OF COMPLIANCE I

I ioc m '

FOR RADIOACTIVE MATERIALS PACKAGES U

I 1.aL CERTIFICATE NUMBER

b. REVISION NUMBER
c. PACKAGE IDENTIFICATION NUMBER d.PAGE NUMBER
e. TOTAL NUMBER PAGES l

9181 3

USA /9181/B(V) 1 2

g 1

2. PREAMBLE l
a. This certificate is issued to certify inat the packaging and contents described in item 5 below, meets tne apphcable safety standards set fortn in Titie io, code l

l of Federal Regulations. Part 71," Packaging and Transportation of Radioactive Material."

i i

i

b. This cert ficate does not re4 eve the consignor from comphance witn any requirement of the regulations of the u.s. Department of Transportation or otner I

apphcabie regulatory agencies, including the government of any country througn or into wnien the package will be transported.

I I

i i

N I

I 3 THIS TIF SISS ON THE BASIS OF A SAFETY ANALYSIS RE RT OF THE P G DESIG O A N

g g

II l

l Nuclear Packaging, Inc.

Nuclear Packaging, Inc. application dated g

j 1010 South 336th Street dated March 31, 1983, as supplemented.

y g

Federal Way, WA 98003 g

l

~

l i DOCKET NUMBER "

f],qjg) 4 CONDITIONS This certificate is conditional upon fulfilhng the requirements of 10 CFR Part 71. as apphcable, and the conditions specified below.

l l

(a) Packaging p

1 a

I (1) Model Nos.:

PAS-2 and PAS-2A C,

l l

llI (2) Descfiption-X l

~

lg l

\\

l The. packaging consists of ~an'outerIverpack, inner overpack, optional l

~

i secondary containment.vess_el'(Model No.; PAS-2A), sample: shield, and a g

i sample vial.

The' outer.' foam fillediove'rpack is constructed identical I

\\

The,the Model,NocN-55 overpack (DocketNoi 9070), 32'700 x 48" high.

N to

^ 2 l

inner overpack~ consists of.a Dep'artment.of Transportation Speciff-N I

l cation 17H steel drum 11ned.with rigid polyurethane foam cut to fit l

~

4 g

the outsideidimensions'of the secondary containment vessel.

The p

g optional secondary containment-vessel is fabricated,from carbon or p

g stainless steelE(17.7" OD x 2413/4":high). and is provided with a Viton l

l 0-ring and eight, 5/16"~ cap.; screws ?'The ' secondary ~ containment vessel I

i is equipped with a test port.

The sample shield consists of a lead I

'l filled steel weldment (16.5" OD x '22.75" high).provided with four l

l shielded wall penetrations and a shielded lid'(all gasketed with Viton p

g 0-rings). E The 3-3/4" ID x 8-1/4" high sampleashield cavity contains a y

g valved sample vial surrounded by absorbent vermiculite and lead shot.

l l

The vial may contain about 50 milliliters of liquid (reactor coolant R

I water sample).

The gross ~ weight;of the package is approximately 2,400 l

,1 pounds.

I I

i (3) Drawi ngs i

I I

l The packages are constructed in accordance with Nuclear Packaging, I

I Inc. Drawing Nos.:

X-20-220D, Sheets 1 through 4, Rev. E and X 1 l

200D, Rev. C.

l i

i 1

I l l I

l l

l

' l I

l I

I 8606240484 860617 I

l PDR ADOCK 07109181 I

l C

PDR I

l l

l l

ll

.- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -. =

l i

l 9" **

conomons (continued)

U *

  • C " " "EC " GR' C * "^'S
  • I l

Page 2 - Certificate No. 9181 - Revision No. 3 - Docket No. 71-9181 l

I I

I I

I I

I 5.

(b) Contents I

I I

(1) Type and fonn of material l

1 i

l Radioactive material in the form of liquid coolant sample obtained l

I from a reactor coolant system.

I I

I f

(2) Maximum quantity of material per package l

l l

l 50 milliliters with a thermal heat load not to exceed 3.0 watts.

g I

p I

6.

In addition to the requirements of Subpatt G of 10 CFR Part 71, each package i

I prior to first me rnst meet the '~a'cceptance~ tests and criteria specified in I

l Section 8.1, m;t be maintai~ned in 'accordhrice fwith Section 8.2, and prepared for I

i shipment in decordance,wi,th-Section 7.0 of the appl.ication.

The sample vial l

l must be annually leakstes'ted to the requirements of 'LT212 (Appendix 8.3.2).

y 0

I l

7.

The statement of acceptance in NUPAC's test, Assembly Hdif'um Sniffer Test for I

I the NUPAC PAS-2 Packagings(5.1, LT-16, Rev. 2, March'951984) must be replaced I

~

l by the following',' acceptance'; criteria:

For each-assembly to'have an acceptably j

l low leakage rates /the detection equipment must beicapable of* detecting a leak of l

10_4sec/sec orfsmaller. AnyidetectedxTeakag'e fate / greater 'tKan the acceptance g

i i

I criteria prior,to first use isinot ac'ce'ptable.R 4 V

y Q \\ Q&A lllcf 3

l I

1 8.

Prior to firstbuse of dach package. the leake. tests sp5cified:as Notes 8 and 14 I

)

l on Drawing No.fX-20-220DC Rev.(C:m'usti@be~phrformed;?as required.

l V

I en. w u F

u s

1 i

The package authorized}bylthis certificate)fs l

9.

general license ppovisions;of)10:CFRiSW.12&, hereby' approved for use under the g

O W

g Ii m

sw s y

,y y

J 10.

Expiration date:

March 31,1989.

g "". 4 l

)

REFERENCES f

l

~

1 1

Nuclear Packaging, Inc. application

  • dated. March (31,11983.

I N

  • t in e'

l 1

Supplements dated:

September 9,1983; February 17, March 9, and December 19, 1984; I

l April 9,1985; and June 2,1986.

l 1

l l

FOR THE U.S. NUCLEAR REGULATORY COMMISSION g

I g

I I

r N

Charles E. MacDonald, Chief l

l Transportation Certification Branch l

I Division of Fuel Cycle and l

I Material Safety, FNSS I

l JUN171986 Date:

I I

I I

I I

I I

I I

I I

I

I I

4-M o

UNITED STATES

~,,

NUCLEAR REGULATORY COMMISSION 5

E WASMNGTON, D. C. 20665 C

8

%*****/

Transportation Certification Branch Approval Record Model Nos. PAS-2 and PAS-2A Packages Docket No. 71-9181 By application dated June 2,1986, Nuclear Packaging, Inc. requested that the certificate of compliance be amended to reference the latest revision of packaging drawings.

The applicant has revised Drawing No.

X-20-2200, Sheets 1 through 4, Revision E, to clarify some dimensional requirements and to provide for optional configurations in two areas.

Specifically, the changes to the drawing include defining the tolerance on the 0.58-inch offset dimension of the shield penetrations; relaxing an implied tolerance on the diameter of the shield (16.50 changed to 16.5); clarified the 4.00-inch dimension which refers to the foam thickness at the bottom of the inner overpack; as an option, a chamfer is permitted in the foam of the inner overpack; and also as an option, the removal of an unnecessary recess in the end of the lower shield plug.

The NRC staff agrees with the applicant that these changes have no effect on the package's ability to meet the requirements of 10 CFR Part 71.

22 **l1 Avd a

g Charles E. MacDonald, Chief

)

Transportation Certification Branch Division of Fuel Cycle and Haterial Safety, NMSS Date:

.. -

Retrieved from "https://kanterella.com/w/index.php?title=ML20206F488&oldid=4051118"