ML20129E986
| ML20129E986 | |
| Person / Time | |
|---|---|
| Site: | 07109086 |
| Issue date: | 05/22/1985 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20129D359 | List: |
| References | |
| NUDOCS 8506060651 | |
| Download: ML20129E986 (4) | |
Text
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NRC FORM S18 U.S. NUCLEAR REUULATcRY Cr,IMMISSION m . CERTIFICATE OF COMPLIANCE y io co "
FCR RADIOACTIVE MATERIALS PACKACES 2
t a. CERTIFICATE NUMBER b. REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBER d.PAGE NUMBER e. TOTAL NUMBER PAGES 9086 12 USA /9086/A 1 3 gl
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- a. This certificate is issued to certify that the packaging and contents described in item 5 below, meets the applicable safety standards set forth in Title 10. Code N j ; of Federal Regulations. Part 71.
- Packaging of Radioactive Materials for Transport and Transportation of Radioactive Matenal Under Certain Conditions." l j : b. Tnis certificate does not relieve ine consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or otner jN appiicabie reguiatory agencies. inciuding ine government of any country tnrougn or into wnien tne package wiii be transported. ;E lE
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. ] 3 TH13 CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE OESIGN OR APPLICATION i<
- a. PREPARED BY (Name and Address A b. TITLE AND 10ENTIFICATION OF REPORT OR APPLICATION ,
! : Westinghouse Hittman Nuclear Hittman Nuclear & Development Corporation application lg
- Incorporated dated March 1,1983.
- 9151 Rumsey Road lE E
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c Columbia, MD 21045
. m OCe, 71-9086 E
- c. DOCKET NUMBER % 3 9 .
I : 4. CONDITIONS h 'f " n l This certificate is conditional upon fulfilling the requifernents of 10 CFR Part 71, as applicable, and the conditions specified below.
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lE (a) Packaging '
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d (1) Model No - HN-100 Series 1 !E, q s ~. - Ei -
d (2) Descrip't ion q _ ~
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j A steel encased, lead.shieldeji cask' for low specific activity material .
lp M The cask is a right circulatcylinder 82.5~ inches high by 81.5 inches @
U in diameter. 'The cask cavity is 74.5l inches high by 75.63 inches in R d diameter. The cask' side wall consists of a -3/8-inch . thick inner steel N j
j shell, a 1-3/4-inch .leadnshell, and a!7/8-inch thick outer steel shell. ~The base isLa 4-inch thick. steel plate which'is welded to the lg j inner and outer. steel shells 'of the side wall. A< steel flange is g a welded to the inner and outer steel ' shells of the side wall at the N
'l top. The . lid is 'a 4-inch thick steel plate which is stepped to mate N with the steel flange. The cask closure is sealed by a Viton or N
];l Buna-N 0-ring gasket located between the lid and steel flange. lg j Positive lid closure is accomplished by thirty,1-inch studs and nuts.
- ) The lid contains a centrally located 4-inch stepped steel shield plug. p 1 The shield plug is sealed by a Viton or Buna-N 0-ring gasket, and lE 1 sixteen,1/2-inch studs an'd nuts are used to provide positive closure. N 1 N .
Tie-down is accomplished by four tie-down lugs welded to the cask j] body. There are three casks lifting lugs, three lid lifting lugs, and f
- ) one shield plug lifting lug. The package gross weight is 50,000 ;
a pounds, j 1 iN (3) Drawings
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3 The packaging is constructed in accordance with Hittman Nuclear & llig
/l Development Corporation Drawing Nos. STD-02-028, Revision 7; STD-02-029, Revision 5; and STD-02-030, Revision 4.
- E jN 4 E H E 1 W.
1 i esc 6060651 850522 PDR ADOCK 07109086 lW E C PDR $j g N n
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. CcNDITl:NS (continutd)
N Page 2 - Certificate No. 9086 - Revision No.12 - Docket No. 71-9086 l,
- N :
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- 5. (b) Contents E N
(1) Type and form of material (
n Process solids either dewatered, solid or solidified meeting the E requirements for low specific activity material, in secondary containers. ju (2) Maximum quantity of material per package l 19 Greater than Type A quantity of radioactive material with the weight p
- of the contents, secondary, containers and shoring not exceeding 14,500 f(
pounds except the we.ightrof 'the Tont. Ants in HN-100 Series 1, Unit 5 h Internal' decay heat must not exceed 7 j
N j
must not exceed 6Vthemal watts 6 ,900' Wgpounds.
.6. For any package d a n n g
(a) radiolytically 1containing
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water and/or generate combustible organic gases, substances determination must bewhich made could by E tests and measurements,or by analysis of a representative package such that
~ l N the following" criter:iacare met over a period"of-time ~ thht'is twice the N expected shipm;ent tii3eip p' l b Mt NM (/ik M
(1) The hydrogen genefated' must,b'e limited;to,a molar qu$tity that would
' l y
g be no'more than SLb~ylv'olumeE(oc~eguivalent limits for; other inflam- N rigas .v6id if fresent at STP N l mabl$
(i.e.gno gases),0f1theJse'coiidary morerthan'0.063- ; mores /ft contaip;at' '
14e7: psia and 70*F);N or e% %
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(ii) The secondary'Nnta'i'nerla;{n c'ah ca'vity mushb'e ineked with a diluent !
to assdre\thatixyjenjustW limitedLto'5% by volume in those portions
~
y of the package which-could have-hydfogFnigreaterzthan 5%. N G y ; ll K G r g ,) go N For any packag[e delivered to a carrier ~for transport, the secondary container must be prepared 'fopfshipment in the same manner in'which determination for l s y gas generation is made'. Shipment period begins when the package is prepared y (sealed) and must be completed,within twice the expected shipment time. N 7 #
M - $ r 7 ..[ N (b) For any package shipped within 10 days of preparation, or within 10 days N after venting of drums or other secondary containers, the determination in l, '
(a) above need not be made, and the time restriction in (a) above does not apply. 3 N
- 7. Except for close fitting contents, shoring must be placed between secondary N containers and the cask cavity to minimize movement during nomal conditions of l
trans port. l
.l l b
- 8. The lid and shield plug lifting lugs must not be used for lifting the cask, and k shall be covered in transit. !N m
!B e 9. Prior to each shipment, the packaging lid seals, if opened (or if security seal l L is broken), must be inspected. The seals must be replaced with new seals if ,
inspection shows any defects or every twelve (12) months, whichever occurs
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h firs t. E i
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F, ,____________________________________m_____________4 nrc wa var " " " " * " ' ' ' ' * ~
l . CONDITE Ns (continuxd)
- 1. N I E I Page 3 - Certificate No. 9086 - Revision Na.12 - Docket No. 71-9086 l l I qi .
ll N il N I 10. The package authorized by this certificate must be transported on a motor N I vehicle, railroad car, aircraf t, inland watercraft, or hold or deck of a seagoing E I vessel assigned for the sole use of the licensee. E i I W l I 11. The package authorized by this certificate is hereby approved for use under the jf g ,g a general license provisions of 10 CFR 971.12. g i I N
I 12. Expiration date: March 31, 1988. N I W 5 REFERENCE N dPDr ll lI Hittman Nuclear & Development Corp o Nd h %e V , ration applicat
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il %1 FOR THE U.S. NUCLEAR REGULATORY 3 COMMISSION E l < ~ .n G q N (>^ W H T f Qj Dx Y i. j l l li N
Qj Mh Charles E. Ma'cDodald, Chie ,,
.'~ m N Transportation Certification Branch N
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I '( Division of Fu'el; Cycle and"' E l N F[
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[ .$tefial) Safety, PNSS [' l
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- 74 y . WASHINGTON, D. C. 20555 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 determined 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 determining 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 detemined by. tests and measurements or by analysis of a representative-package -
whether or not. . . ."
~
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 closureFand twice the shipping time must be considered. The calculation requires that the properties of the waste a re known .' These properties may be detemined from test and measurement of representative waste foms or from data that is applicable to the waste form. The determination should be documented and retained as part of the records for the shipment.
M [k -
Charles E. MacDonald, Chief
. Transportation Certification Branch Division of Fuel Cycle and -
. Material Safety, NMSS Date: N2 21BR f
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