ML20125D871

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Certificate of Compliance 9181,Rev 2,for Models PAS-2 & PAS-2A.Approval Record Encl
ML20125D871
Person / Time
Site: 07109181
Issue date: 06/04/1985
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20125D861 List:
References
NUDOCS 8506120493
Download: ML20125D871 (3)


Text

gwwwwwwwwwmm m u s am m m u n n = = m- =* * *m - = = = ====== = === =*== = -= === =5 InY CERTIFICATE OF COMPLIANCE l io Cr.1" Ff R RADl! ACTIVE MATERIALS PACKAOES N

j 14 CERTIFICATE NUMBER b REVISION NUMBER C PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES p

9181 2

USA /9181/B(U) 1 2

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a. This certificate is issued to certify that the packaging and contents descnbed in item 5 below, meets the applicable safety standards set forth in Title 10. Code N

]l of rederai Regulations. Part 71. -Packagmg of Radioacteve Materials for Transport and Transportation of Radioactive Material Under Certain Conditions."

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b. inis certificate does noi reiieve tne consignor from compiiance witn any requirement of tne reguiations of tne u.s. oepartment of Transportation or otner l'

Ji applicable regulatory agencies including tnesgovernment of any country through or into which tne package will be transported.

5 F===kaging, Inc.

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lj Nuclear Pac Nuclear Packaging, Inc. application dated b

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

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Federal Way, WA 98003 E

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E 1l c oOcxET NUuBER 71-9181 E-l 4 CON 0lflONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicabie, and the conditions specified below

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(a)

Packaging

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(1) Model Nos.:

PAS-2 and PAS-2A I

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(2) Description E;

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The packaging consists of an outer overpack, inner overpack, optional j

secondary containment vessel (Model No. PAS-2A), sample shield, and a p

Y sample vial.

The outer foam filled overpack is constm eted identical i

1f to the Model No. N-55 overpack (Docket No. 9070), 32" OD x 48" high.

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The inner overpack consists of a Department of Transportation Specifi-i 1

cation 17H steel drum lined with rigid polyurethane foam cut to fit

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the outside dimensions of the secondary containment vessel. The y

al optional secondary containment vessel is fabricated from carbon or y

l stainless steel (17.7" OD x 24 3/4" high) and is provided with a Viton I

al 0-ring and eight, 5/16" cap screws. The secondary containment vessel E!

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1; is equipped with a test port. The sample shield consists of a lead Ei l

filled steel weldment (16.5" OD x 22.75" high)(all gasketed with Viton [

provided with four

}i shielded wall penetrations and a shielded lid g

3 0-rings).

The 3-3/4" ID x 8-1/_4" high sample shield cavity contains a p

1 11 valved sample vial surrounded by absorbent vemiculite and lead shot.

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

1 watersample).

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

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pounds.

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J, The packages are constructed in accordance with Nuclear Packaging, D awin Nos.:

X-20-2200, Sheets 1 through 4, Rev. D and X,

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B506120493 850604 J,

PDR ADOCK 07109181 f'

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CONDITE:NS (continuid) l:

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f.Page 2 - Certificate No. 9181 - Revision No. 2 - Docket No.

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71-9181 li L I ll t l li Ll f{

5.

(b) Cantents (1) Type and form of material li t

l Radioactive material in the fom of liquid coolant sample obtained t

1;l from a reactor coolant system.

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t fl (2) Maximum quantity of material per package

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1' 50 milliliters with a thennal heat load not to exceed 3.0 watts.

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In addition to the requirements of Subpart G_of 10 CFR Part 71, each package t!

l prior to first use must meet the acceptance tests.and criteria specified in L;

f' Section 8.1, must be maintained in accordance with Section 8.2, and prepared for h

1 shipment in accordance with Section 7.0 of the application.

The sample vial t3 1l must be annually leak tested to the requirements of LT-12 (Appendix 8.3.2).

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The statement of, acceptance in NUPAC's test, Assembly Helium Sniffer Test for i[t!

f the NUPAC PAS-2 Packaging (5.1, LT-16, Rev. 2, March 9,1984) must be replaced j

by the following acceptance criteria:

For each assembly to have an acceptably 10W 1eakage rate, the detection equipment must be capable of detecting a leak of

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10-4 scc /sec or smaller. Any detected leakage. rate greater than the acceptance t:

T criteria prior to first.use is not acceptable.

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Prior to first use of ~each package the. leak ' tests specified as Notes 8 and 14 (i

f on Drawing No. X-20-2200, Rev. C must be performed, as required.

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The package authorized by 'this certificate is hereby approved for use under the t:

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general license provisions. of 10 CFR 971.12.

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Expiration date: March 31,1989.

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h REFERENCES 3l Nuclear Packaging, Inc. applicatior$ dated Mdch 31, 1983.

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1 Supplements dated:

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

f and April 9,1985.

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FOR THE U.S. NUCLEAR REGULATORY COMMISSION y

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Charles. MacDonald, Chief y

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Transportation Certification Branch I

T Division of Fuel Cycle and 5

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Haterial Safety, NMSS E

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UNITED STATES

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' ;y WASHINGTON, D. C. 20555 g

NUCLEAR REGULATORY COMMISSION 3,

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Transportation Certification Branch Approval Record Model Nos. PAS-2 and PAS-2A Packages Docket No. 71-9181 By application dated April 9,1985, Nuclear Packaging, Inc. requested minor changes to the package operating procedures.

The NRC staff agrees with the applicant that these minor changes have no effect on the package's ability to meet the requirements of 10 CFR Part 71. The actual leak testing requirements for the package remain the same.

'fA u Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date: M04 g

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