ML20128N412
| ML20128N412 | |
| Person / Time | |
|---|---|
| Site: | 07109074 |
| Issue date: | 05/22/1985 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20128N400 | List: |
| References | |
| NUDOCS 8506030267 | |
| Download: ML20128N412 (4) | |
Text
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""Sf" CERTIFICATE OF COMPLIANCE l
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FOR RADCACTIVE MATERIALS PACKA7ES I
1 a CE.4TIF.iCATE NUMBER tt REVISION NUMBER
- c. PACKAGE IDENTIFICATION NUMBER d.PAGE NUMBER
- e. TOTAL NUMBER PAGES I gl 9074 5
USA /9074/A 1
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'1 Uj 2. PREft.MBLE ll a This certificate is issued to certify that the packaging and contents described in item 5 below, meets the apphcable safety standards set forth in Title 10. Code l
ll of Federal Regulations. Part 71. " Packaging of Radioactive Matenals for Transport and Transportation of Radioactive Matenal Uncer Certain Conditions?
- b. This certificate does not reheve the consignor from comphance with any requirement of the regulations of the U S. Department of Transportation or other l l apphcable regulatory agencies, including the government of any country through or into which the package will be transported.
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ANEFCO, Incorporated ANEFCO, Inc. application dated January 31, 1983, j'
P.O. Box 433 as supplemented.
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Ridgefield, CT 06877 E
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C 71-9074
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I I a. CONDITIONS
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l This certificate is conditional u'
'ulfilhng the requirements of 10 CFR Part 71, as apphcable. and the conditions specified below
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p (a) Packag.. 3 g
I lg (1) Model No.:
AP-100 E
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(2)
Description
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A steel encased, lead shielded cask-for low specific activity material.
ig The cask is a right circular cylinder 92-1/4 inches height by 64 li inches in diameter. The' cask cavity is 87 inches deep by 60 inches i
diameter.
The cask ~ consists of:two, 3/8-inch thick cylindrical steel N
shells' surrounding a 1-1/4-inch thick lead shield. The tase consists j
i of two,-3/8-inch thick circular steel plates separated by a 1-1/4-inch g
lead shield, and welded toithe cylindrical walls using full penetration p
welds. 3The cask cover is a welded circular steel construction surrounding i
a 1/2-inch lead shield.
The cover is secured to the cask body usir?g N
32, 3/4-inch diameter bolts which feed through the cover to a steel N
bolt ring which is welded to the cask body.
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The cask closure is sealed by two ethylene propylene gaskets.
Four p
l symmetrically spaced lugs are welded to the cask body for lifting and B
I tie-down.
Three removable, threaded eyes are attached to the cover N
j for lifting.
The package gross weight is approximately 28,000 pounds.
l (3)
Drawings l
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j The packaging is fabricated in accordance with ANEFC0 Drawing Nos.
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I 00054-A, Rev A.; 00054-B; and 00054-C, Rev. D.
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Page 2 - Certificate No. 9074 - Revision No. 5 - Docket No. 71-9074 E
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'5.
(b) Contents
!y lN i l i l (1) Type and form of material E
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l Solids and solidified waste which meet the requirements for low specific f
.lg activity material.
Solidified waste must be packaged in secondary
!y ju inner containers within the cask g
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ll (2) Maximum quantity of material per package E
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l Greater than type A quantity, of radioactive material with the weight
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of contents and seconda~ry contain'ers not to exceed 10,000 pounds j
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(a) For any package contain'ing water ard/or org'anic' substances which could in E
llf i l radiolytically generate combustible gases, determination must be made by 5
I tests and measurements or by analysis of a repre'sentative package such that 1
l the following2 criteria are met over a period of time:that is twice the q
expected spi,pmenktime:
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!I (1) The. hydrogen' generated must be limited jto a molar quantity that would ju mable,fmore thanl5Lbhvolume;(or equivalent limits for other inflam-l be no
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I gases) off the7 secondary contaigerigas void if present at STP l
(i.ei., no moreithan' 0'.063;gemoles/f t f at 14.7 psia'and 70*F); or
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ju (ii) The secondary. container anicask~ cavity must;be inerted with a diluent g
ll to ' assure 'thatjoxygen;must be! limited' to' 5%.by vol'ume in those portions E
il of the package which could have. hydrogen greater ~than 5%.
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For any package delivere'd -to~ a carrier for.f.~. transport,'the secondary container y
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must be prepared for shipment'in 'the'same manner in which deterr'.ination for q
gas generation <is made.
Shipment, pe'riod' begins when"the package is prepared g
ll (sealed) and nust be completed'within twice the expected shipment time.
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I (b)
For any package s'hihped within 10 days of preparation, or within 10 days l
1 after venting of drums >or other. secondary. containers, the determination in g
k (a) above need not be made,'and.the time restriction in (a) above does not y
lI' a pply.
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j 7.
The cover lifting eyes nust not be used to lift the cask, and shall be removed M
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prior to shipment.
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5 Prior to each shipment, the packaging lid seals must be inspected.
The seals must be replaced with new seals if inspection shows any defects or every twelve (12) g 8.
g Il months, whichever occurs first.
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9.
Fabrication of additional packaging after March 31, 1983 must be constructed of 1
ASTM A-516, Grade 70 normalized fine grain practice steel in lieu of ASTM A-36 g
al s teel.
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Page. 3 - Certificate No. 9074 - Revision No. 5 - Docket No. 71-9074 l i\\
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N-I 10.
The package authorized by this certificate must be transported on a motor E
l vehicle, railroad car, aircraft, inland water craf t, or hold or deck of a seagoing l
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vessel assigned for the sole use of the licensee.
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- 11. The package authorized by this cartificate' is hereby approved for use under the 4
general license provisions of 10 CFR 971.12.
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12.
Expiration date:
March 31, 1988.
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g REFERENCES g
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ANEFCO, Incorporated application dated 'Januhy231,il983.
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'f lE-
@i Supplement dated:
October 14',,1983.
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,3 FOR THE U.S. NUCLEAR REGULATORY COMMISSION
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!g Charles / E flacDonald,-Chief J
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N-tu.iTransportation, Certification Branch B
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C?'TDivision of Fuel" Cycle and <
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o-UNITED STATES 8 y)g Ik NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555
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Transportation Certification Branch Approval Record Combustible Gas Mixtures Conditions were imposed on packages containing water and/or organic substances to limit the accumulation of radiolytically generated gases over the shipping period to preclude the possibility of significantly reducing the packaging effectiveness due to explosion.
Part of the conditions included "...it must be detemined by tests and measurements of a representative package whether or not...."
There is no reason to believe that calculational methods could not be used as means of detemining gas generation. So as not to preclude a valid analysis, part of the condition to limit the accumulation of radiolytically generated gases is revised to read "...it must be determined by tests and measurements or by analysis of a representative package s
whether or not...."
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The analytic approach involves detemining the hydrogen generated in the waste by radiolysis based on the absorbed dose of the waste over a given period of time. To satisfy the condition to preclude a combustible mixture, the period since closure and twice the shipping time must be considered. The calculation requires that the properties of the waste are known. These properties may be detemined from test and measurement of representative waste foms or from data that is applicable to the waste fom.
The determination should be documented and retained as part of the records for the shipment.
W wh Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date: W2225 L