ML20215D147

From kanterella
Jump to navigation Jump to search
Certificate of Compliance 9151,Rev 10,for Models HN-100 Series 3,CNS 14-170 Series Iii,Ln 14-170 Series 1 & NES-1
ML20215D147
Person / Time
Site: 07109151
Issue date: 12/12/1986
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20215D135 List:
References
NUDOCS 8612160228
Download: ML20215D147 (7)


Text

-_------mmmmmmmm- = = = - - - mar c.nnswmq mac romu 418

  • =

'o CFR " CERTIFICATE GF CSMPLIANCE U.S. NUCLEA3 E EGULATCC FlR RADl? ACTIVE MATERIALS PACKAGES E 14 CERTIFsCATg 0 REV6SiON NUw ER c PACKAGE ICE # CAT Q N BER d PAGE NUMBER e TCTAL NL.N8E4 PAGES

' t PRuustE T a rnis cert,ticate .s .ssuee o certif y inat tne pacnaging anc contents oeseneeo in item s oeio*. meets tne aconcacie safety stanoaros set tonn in Titie io. coo. T of Feoeral Reguiahons. t' art T1. -Pacnaging ano Transportation of Radioactiv3 Material" ,[

o Tn.s ceniticate ooes not rei, eve ene cons,gnor from comonance . in any recuirernent of tne reguianons of tne u s. o.oanment of Transponation or otner E!

, appocacie reguiatory agencies. incivoing ine governmeni or any country inrougn or into .n en tre pacxage .iii e. transponeo. El l

E i

%'O 3 TH*S CERTIFICATE i$ ISSUED ON THE BASJS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE CESIGN OR APPUCATION a ISSUED 70 meev emr Moresse b TITLE ANO 4CENTflCATiON CF REPORT OR APPUCATION I lEj Westinghcuse Hittman Nuclear h l Westinghouse Hittman Nuclear Incorporated ,E Incorporated application dated January 9,1986, as I i

9151 Rumsey Road Columbia, MD 21045 e OOC ET NuueEa supplemented, 71-9151 f

i

  • E a CO~oiTiONS in,s cenit.cate is cono t.onarupon tuitiinns tne reau,rements of to cFR part ri. as apoocatie. ano tne conoit, ens specir..o oeio.

g[

s M i 'El (a) Packaging ff E:

(1) Mcdel Nos.: HN-100 Series 3, CNS 14-170 Series III, LN 14-170 i Series 1, and NES-1.

@5; (2) Description 3

Steel encased, lead shielded casks for low specific activity material. is:

j The casks are right circular cylinders 81-1/2 (cr 81-5/8) ir.ches high !

by 81-3/4 (or 81-1/2) inches in diameter. The cask cavities are 73- A 3/8 (or 73-5/8) inches high by 75-1/2 inches in diameter. The cask I l sidewallsconsistscfa3/8-inchthickinnersteelshell,a1-7/8-(or}

! 1-3/4-) inch lead shell, and a 7/8-inch thick cuter steel shell. The i i base is comprised of two, 2-inch thick steel plates welded together to 1

fern a 4-inch thick base which is integrally welded to the inner ard J outer steel sheils of the side wall. A steel flance is welcea to the 4 inner and outer steel shells of the side wall at the tcp. The lid is 8 l ccmprised of two, 2-inch thick steel plates, which are stepped and l welded together to mate with the steel flange. The cask closure is j;p i sealed by a Neoprene gasket located between the lid and steel flange, il l positive closure of the lic is accomplishec by eight,1-3/a-inch #

l rachet binders. The lid contains a centrally located shield plug ccmcrised of two, 2-inch thick steel plates and one, 1-inch thick f..

steel plate stepped and weldec. The shielc plug is sealed by a l:eepren*

l gasket, and eight, 3/4-inch studs ana nuts are used tc provice pcsitive closure. The packagings are constructed cf A-516. Grace 70 or A-537,

' :l Class ?, carbon steel. The outer shell wi!! have a minimum yield l strength of 46,000 psi.

, lf.

Mcde! t' umber CD, inches Lead Tk, inches f

HN-100 Series 3 81-3/4 i-7/8 i C:'S14-170 Series III 8?-i/2 1-3/4 LN 14-170 Series 1 C1-3/4 1-7/E 9l E

NES-; Ei-3/4 i-7/8 j 8612160228 861212  !

Bl

- PDR ADOCK 07109151 PDR - _. - -- -- -xxstracaravxxxacuatrucxcxcacu um xr.J

m i-----------------------------------------------------9

.9 CONDmONS (contmued) .E l

1 Page 2 - Certificate No. 9151 - Revision No. 10 - Docket No. 71-9151 j

'n I i I

5.(a) (2) Description (contfrued) lpg I'  :

l Tie-down is accceplished by four tiecdcwn lugs welded to the cask lpE g

l body. There are four cask lifting lugs, three lid lifting lugs, and one shield plug lifting lug. The package gross weight is approximately i j

I 53,000 pounds. !n p l in I (3) Drawings I lE E

l The Model No. HN-100 Series 3 packaging is fabricated in l1 l cccordance with Hittran Nuclear & Development Corp. Drawing i

! Nos.: C001-5-9138, Rev. 10; C001-5-9139, Rev. 8; C001-5-9140, !g, i Rev. 8; C001-5-9141, Rev. 3; CC01-5-9142, Rev. 1; C001-5-9143, p I Rev. 8; and C001-5-9144, Rev. 3. Optional stainless steel E

[ shielding insert in accordance with Drawing Nos.: STD-02-C35, !E I

Rev. A; STD-02-036, Rev. A; and STD-02-037, Rev. 2. j

!g i The Model No. CNS 14-170 Series III packaging is fabricated in l3

, 1 accordance with Chem-Nuclear Systems, Inc. Drawing Ncs.: i l

l# C-110-D-0016, Sheets 1 and 2, Rev. C; C-110-D-0017, Sheets 1 N II end 2, Rev. C; C-110-D-0013, Sheets 1 and 2, Rev. C; and ll C-110-D-0019, Rev. B. jln i

lll The Model Nc. LN 14-170 Series 1 packaging is fabricated in accordance l1 3 il with LN Technologies Corporation Drawing Nos.: 8916 M 2001, p

!N Pev. 0; 8916 N 2002, Rev. 0; 8916 M 2003, Rev. 0; 8916 M 2004, j

l9 Rev. 0; 8916 M 2005, Rev. 0; and 8916 M 2006, Rev. C.

J y

lq, The Model No. NES-1 packaging is fabricated in cccordance with Nuclear p jg Energy Services Drawing Nos. 83E1903, Rev. 1; and 83E1909, Rev. O. 's (b) Contents li' (1) Type and form of material Process sclids, either dewatered, solid or solidified, meeting gl the requirements for low specific activity material, in il secondary containers. M)

(2) Maximum quantity of material per packace l 3 Greater than Type A quantity of radicactive material which may y contain fissile material provided the fissile material dces not exceed the limits in 10 CFR s71.53. The weight of the contents, i'

l optional shield insert, and secondary containers shall not -

exceed 17.800 pounds. When the shield incert is not installed b in the cask, the internal decay heat load shall not exceed 7 q i watts. I! hen the shield insert is installed in the cask, the p internal decay hect load shall not exceed 28 watts. d b

E t ,m, f b k-__-- _._.= _ mm.u.m. gem.u,,,j g m , .m m m m ,,m m gf

mm _ _ _

l .

j I

CONDmONS (continued) l

! Page 3 - Certificate No. 9151 - Revision flo.10 - Docket No. 71-9151 I

I

!))

ll l

6. (a) For any package containing water and/or organic substances which could I radiolytically generate combustible gases, determination must be made by ;l l i i tests and measurements or by analysis of a representative package such that lE i the following criteria are met over a period of time that is twice the l expected shipment time: j!g I !g I (1) The hydrogen generated must be limited to a molar quantity that would ji l be no more than 5% by volume (or equivalent limits for other inflam- lI g mcble gases) of the secondary contairerg gas void if present at STP i (f.e., no more than 0.063 g-moles /ft at 14.7 psia and 70 F); or jlE i 'n I (ii) The secondary container and cask cavity must be inerted with a diluent p I to assure that oxygen must be limited to 5% by volume in those portions 9 l of the package which could have hydrogen greater than 5%. j

! For any package delivered to a carrier for transport, the secordary container '

I must be prepared for shipment in the same manner in which determination for p I aas generation is made. Shipment period begins when the package is prepared g I fsealed)andmustbecompletedwithintwicetheexpectedshipmenttime, li lI >

ll lq (b) For any package shipped within 10 days of preparation, or within 10 days after venting of drums or other secondary containers, the determination in j

i 11 (a) above need not be made, and the time restriction in (a) above does not !g, I apply.  !

\ %g j, 7. Except for close fitting contents, shoring must be placed between secondary jg containers and the cask cavity to prevent movement during normal conditions of j(5 transport. l, llq l iN

0. The lid, shield plug, and cask lifting lugs must be covered in transit to preclude;

. their use as tie-down devices.  ;

I ,

9. Tcrque requirements for closure fasteners.

(a) Primary lid ratchet binders must be torqued to 175-200 ft-lbs.  ;

(b) Secondary lid bolts must be torqued to 120 10 ft-lbs.

i e 3

ya

r i

i pl F

i a y

4 jgl 9

  • si

,axxx-mcrxrrmcaca-Eaa merzhammwszazemmm airrnum myrmh)

li l

'j CONOlTIONS (continued) l l Page 4 - Certificate No. 9151 - Revision No. 10 - Docket No. 71-9151 l !jn I .

II I 10. In addition to the requirements of Subpart G of 10 CFR Part 71: ji I

N I

(i) Prior to each shipment, the packaging lid seals, if opened (or if security E i seal is broken), must be inspected. The seals must be replaced with new i seals if inspection shows any defects or every 12 months, whichever occurs ljg I first. lg I

I I I

(ii) Each package must meet the Acceptance Tests and Maintenance Program of: lh jN g Model No. FN-100 Series 3 1

& Section 7.0 of the application. Gamma scan for the shielding acceptance llt g may be based en lead equivalence for lead and steel with all readings j

i

't within 2.3 inches +107, on a 4-inch grid. j l Mcdel No. Cf'S14-170 Series III I

)

19 I Section 4.0 of Chem-Nuclear Systems, Inc. Document No. CNSI 9151-SI, I Rev. 2. )N 4

l

!5 Model No. LN 14-170 Series I j

'n l' lI LN Technologies Corporation Prccedures KM-011, Rev. G; WM-012, Rev. H; WM-013g ll Rev. F; and WM-014, Rev. K.

lI l lW iF 13 Model No. NES-1 :8 4 iR NES Procedures 33A1902, Rev. O and 83A1907, Rev. O, except that secondary I lid gasket dimensicns must be in accordance with the packaging drawings. y

[g I 't j

11. Seals which shcw any visual defects (cracking, gouging, tearing, etc.) must be repaired in accordance with:

}

j Model Nos. HN-100 Series 3 and CNS 14-170 Series III #

h jil Note No. 3 en Hittman Drawing No. C001-5-9138, Rev. 10; or, replaced with a new pi

$ seal. d 3

(i Model No. LN 14-170 Series 1 l$q g

LN Technologies Corporation Procedure WM-012, Pev. H, Secticn 7.1 (joint !i angle cust be approximately 45 ); or, repiaced with a new seal. El Model No. NES-1 fa

+

HES Precedure 83A1907, Rev. O, Section 4, except that seccrdary lid gasket D

! dimensions must be in accercance with the packaging drawings; or, replaced with j a new seal. g

g 12. Thepackageauthorizedbythircertificatemustbetransportedonamotorvehicle,h railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vessel a

'y4 assigned for the sole use of the licensee. y

  • i 3

?

4

-- - - -.. n n. _ .w.-.w w.w a.uzw .. _ - - _ d

ymm mm m m m - - - - .- - - - - - - - xx- - - .,,_ -, ., _w, ,, ,, ,,x- ,x ,, ,,,,,,,c, 11 l .e CONDITIONS (continued) E l Pago 5 - Certificate No. 9151 - Revision No. 10 - Docket No. 71-9151 ,

I I 'h i'E I 13. The package authorized by this certificate is hereby approved for use under the s 1

general license provisicns of 10 CFR 571.12.

\ 3

\

lh i I

14. Expiration date: June 30, 1987.

l REFERENCES lE I !p g I Westinghouse Hittman Nuclear Incorporated application dated January 9,1986.

\ IN

\

't Supplement:: dated: June 23 and July 22, 1986.

1]1 Chem-Nuclear Systems, Inc. supplements dated: l5 N November 16, 1982, and June 9, i i September 5, and November 19, 1966. jg, 18 3

NUS Process Services supplements dated: June 29 and September 12, 1983; December 7, j]y 1984; and January 11, May 7, and June 14, 1985.

E

!N lil Nuclear Energy Services supplements dated: February 26 and May 12, 1966. E LI jg NL Technologies Corporation supplement dated: November 20, 1986. l FOR TiiE U.S. NUCLEAR REGULATORY C0f7ISSION ,

'E i

Charles E. Mac0cnald, Chief ;E lg ig Transportation Certification Cranch Division of Fuel Cycle and j

jg Material Safety, NMSS )Q Date: DEC1 2 386 g

I

, s$

.g e

i d l

y

( N B

f i i I 5 Sl l

k,

?

k h y

it - w.u m - s m m mex a +w w w ,m m ,2.xww , ,m m ,m ,y ,,-_ w m m m wm jj

~

, ps e "cg -

y, pg UNITED STATES e' o NUCLEAR REGULATORY COMMISSION

=

3 [ i m, 5 WASHINGTON, O. C. 20555

s. I  %

% .a+...f -

Transportation Certification Branch Approval Record -:

Model Nos. HN-100 Series 3, CNS 14-170 Series III, A LN 14-170 Series 1, and NES-1 Packaces Docket No. 71-9151 m

a -

By applicaticn dated November 20, 1986, LN Technologies Corporaticn requested a the Model Nc. NUS14-170 Series I cask be revised to Model No. LN 14-170 -

Series I cask. On September 30, 1986, Lcndon Nuclear Services purchased all E

the outstanding stock of the NUS Process Services Corporation. The two -

organizations are being merged into a new company called LN Technologies 7 Corporation. The Operating Procedures, Leak Test Precedures, Maintenance Procedures, Gamma Scanning Procedures, and the cask drawings have been revised i to reflect the name change. _

In addition, the procedures have been revised to reflect approval cenditions --

ccncerning bolt and ratchet binder torquing recuirements. Scme other minor 2 changes have been made which have no significant effect on the ability of the -

cask design to meet the requirements of 10 CFR Part 71. -

'k Charles E. MacDonald, Chier -'

Transportation Certification Branch i Division of Fuel Cycle and i Material Safety, NNSS C

Date: DEC 121996 r

A ii

-~

9 m

.l 1

mm

> . p HG 3

y,_ , o,, UNITED STATES

( l-

) #, g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 l

\, -...../

Trcnsportation Certification Branch Aporoval Record Mndel Nos. HN-100 Series 3, CtJS14-170 Series III, s

LN 14-170 Series 1, and NES-1 Packages

, Docket No. 71-9151 By application dated June 9,1986, as supplemented September 5 and November 19,_1986, Chem-Nuclear Systems, Inc. submitted, for incorporation into the certificate of ccmpliance, "as built" packaging drawings, operating crocedures, initial acceptance procedures, and maintenance program for the Model No. CNS 14-170 Series III packaging.

The "as built" drawings were reviewed and.found to contain all the pertinent material specifications and dimensional information given on the previously referenced packaging drawings. The operating procedures, acceptance test and maintenance prograns were reviewed and found to be acceptable.

All the above documents have been incorporated, by reference, into the certificate of compliance.

Condition 5(a)(2) and (3) of the certificate of compliance had been changed withcut regard to the previously approved Chem-Nuclear Systems, Inc.

supplement dated Ncvember 16, 1982, which provided an analysis substantiating the use of A-516, Gr. 70 material having a minimum yield strength of 46,000 psi. The certificate of ccmpliance has t'een changed accorcingly. ,

The above changes do net effect the ability of the cask cesign tc meet the requirements of 10 CFF, Fart 71.

eLaP Charles E. MacDonald, Chief A

Transportation Certification Branch Division of Fuel Cycle and Yateriai Safety, KhSS Date: CEC 12 W