ML20214J409
| ML20214J409 | |
| Person / Time | |
|---|---|
| Site: | 07109183 |
| Issue date: | 07/30/1986 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20214J396 | List: |
| References | |
| NUDOCS 8608140626 | |
| Download: ML20214J409 (4) | |
Text
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u.s. NUCLEAR REGULATORY COtttMSSION nne roms m I
om CERTIFICATE CF CCMPLIANCE r
I to crR n FOR RADIOACTIVE MATERIALS PACKAGES l
i.a cERrwicATE NUMBER
- b. REVISION NUMSER
- c. PACKAGE IDENTIFICATION NUMBER d.PAGE NUMSER
- e. TOTAL NUMeER PAGES 9183 4
USA /9183/B( )F 1
3 g
1 : PREAM8tE l
- a. This certificate is issued to certify that the packaging and contents descni,ed in item 5 below, meets the applicable safety standards set forth in Title 10. Code l
of Federal Regulations. Part 71. -Packaging and Transportation of Radioactive Material."
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- b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other I
apphcabie reguistory agencies. inciuding ine government of any country tnrough or into whien the package wiii ne transported.
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l 1 g i g is as guEoN Tu sAsis or A sArErv ANAtysis reg,7gr,NgGE,ogGNgego cgoN I
i Nuclear Assurance Corporation Nuclear Assurance Corporation application dated l
l 5720 Peachtree Parkway June 30,1984, as supplemented.
I Norcross, GA 30092 I
I C m,71-9183 I
c; DOCMET NUWeER t
- 4. CoNOITiONs
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This cattificate is conditional upon fulfilhng the requirements of 10 CFR Part 71, as apphcable, and the conditions specified beiow.
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(a) Packaging i
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I (1) Model No.:. NAC-1 g
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(2) Deschi'ption'N[x f-1 1
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-1 l
Al steel and leadyshieldedcibippingscask'.~ Jhe cask is a right circular cyJinder with upper 7and lower steel enca; sed balsa impact limiters.
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The,overall dimensions are'i 214 inches;in length and 50' inches in I
diameter, eThe ' gross 'weighFof-the caskii's approximat'ery 49,000 pounds.
I Th e_ i nners cayi tyyi s:178ti nche s _l ongf an'dyl3. 5 i nche s in! di amete r.
The I
thicknesssoP the inneFsheld is 5'/.16sinch.and?T-l/4 inches for the
=
l outer shel:lf.S'The,twoestain'less Isteel' shellsTa're weldid to a 2-inch i
thicle. stain 16'ssisteelcshield discEat. the bottom.
The' annulus between I
the-inner andiouter shells 11s fi1>ledhwith ' lead (max'mlead thickness
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6-5/8 inches, minimum 5 inches)'.x 1
+
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The liAfs. stainless steel / frustum of cone 7.5-incies thick.
The lid l
is secured.to, the cavity flange'by six, ASTM-A320, Grade L43,1-1/4 inch i
diameter bolts.
The seal is provided by twoipolytetrafluoroethylene l
l 0-rings.
Four trunnions, two located-on either side of the upper or I
lower impact limiter, are provided Other cask features include two I
drain valves located innthe bottom, shield disc, vent valve, head l
closure gasket leak check valve, and rupture disc - pressure relief i
valve system located in the cavity flange, For transport the cask may i
be enclosed in an expanded metal cage.
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(3) Drawings l
l The Model No. NAC-1 shipping cask is constructed in accordance with i
Nuclear Fuel Services, Inc., Drawing No. E 10080, Sheets 1 through 4, q
Rev. 21, as modified by Nuclear Assurance Corporation letter dated l
July 24,1986.
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l 8608140626 860730 i
C PDR l
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'"pm NA CONDmONS(continued)
U.S. fdUCLEAR REGULATORY CONm!SSION l I
I Page 2 - Certificate No. 9183 - Revision Nc. 4 - Docket No. 71-9183 g
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(b) Contents l
(1) Type and form of material l
I (i) Clad, irradiated metallic natural uranium fuel rods.
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(if ) Solid nonfissile irradiated hardware.
l (2) Maximum quantity of material per package l
l The cavity content must not,3xc_eed a thermal decay heat load of 625 g
watts and a weight,o@rin the 'cTsk00l4bbit luding weight of component spacers I
(or fuel basket uset aiuttf to limit movement of contents I
during shipment fuel rods are additi%
limited as follows:
j (1) 21 in t rods or 10 encapsulated (defecjt ve) rods l
(ii) 1,60tFMWD/MTU average burn-up 4
I coQa.' e'd c at least 730 days after,irrs8iation I
(iii) s j
i (c) FissileC15di j
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b Ks4 jM l
The cask cavity must be dryr(nd(free @gnter) 6.
heiicdelivered to,,,'a carrier for y
transport.
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$1 l
' A[, / /
As needed, approp'riathcom, pone %h h
h0 9 I
nt'espetesT basketfand antal spacers for I
7.
shipment of fue'T rods $msstAbei p j (th @l(k caitt;p? to 135f t movement of l ds contents during % n $ W ' S "
accide t-cruyditichst e a
rt. * '
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dCand miditt'ained h)a dry condition in The neutron shielWtanksimust be drai 8.
I accordance with Section 7 of the appTicatic'n,'as/ supplemented.
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- W+ ~
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I In lieu of the requirements of 10 CFR 571.87(e), theld)censee must perform l 9.
periodic maintenance and testing of 0-rings, dra.in and vent ball valves, relief i
valves, and rupture discs of the cask as indicated in the table given below.
l During inactive periods, the maintenance and testing frequency may be disregarded I
provided that the package is brought into full compliance prior to the next use I
of the package.
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- 9c Fon u sia^
U.S. MUCLEAR REGULATCRY COMMISSION
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l Page 3 - Certificate No. 9183 - Revision No. 4 - Docket No. 71-9183
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I Cask Component
- Period Test / Action I
I Ball Valve Each shipment Hydro test to 30 psig*
l Ball Valve Annually Replace seats and seals I
f I
I 0-rings Each shipment Test to 30 psig*
I 0-rings Annually Test to 100 psig*
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Inner Containment Vessel Annually Test to 100 psig*
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Cavity Relief Valve Annually Test at set point hh eplace Cavity Rupture Disc R
An a
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I' Neutron Shield TankJ ip
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l Rupture Disc Q
Annually Replace f
Impact Limit Annually gT to 5 psig*
Nationso pressure drop I
10Mnnte test pe(riod.
- There trust (be no visual'*(pressure gauge i
l Otherwi se, b
corrective,ponent un'deg,, test dutfugsaction musLtgbe takerwand thes I
P for the com af y
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as the component meets 2the'speiMidd t'e a(Test to p{rissures equal tol l :
I or greaten,than thoseEi~ psi'catedJ '
f, I
10.
Fabrication of additi ac 9 i s nA t'liorl d '
i 11.
The package authorized t
ocerti her approvD for use under the I
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general license poivisioni)6ft0U'CFif71d125*7 W
uO:llD*'bR&f'
)h l
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l 12.
Expiration date:
September 30, 1989Q-@
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vy[]
g-l REFERENCES D
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l N_s Df I
,x Nuclear Assurance Corporation appTibation ~dateqlune 30,1984 l
l Supplements dated:
September 10, 1984; and July 24, 1986.
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l-FOR THE U.S. NUCLEAR REGULATORY COMMISSION l
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M I
lll Charles E. MacDonald, Chief I
lg Transportation Certification Branch I
- y Division of Fuel Cycle and l
lll Material Safety, PNSS l
l Il Date:
AL 3 01986 I
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_1
neery UNITED STATES y
NUCLEAR REGULATORY COMMISSION o
lr, j
WASHINGTON, D. C. 20666 h,,
,o Transportation Certification Branch Aparoval Record Model io. NAC-1 Package Docket No. 71-9183 By application dated July 9,1986, as supplemented July 24, 1986, Nuclear Assurance Corporation proposes to attach auxiliary shielding to the Model No. NAC-1 cask in the form of a 1/4-inch thick copper plate within the neutron-shield tank at the time of manufacture.
This auxiliary shielding will reduce the yxternal gamma k%f5 rates by at least 35%
(viz:
(0.635 cm)(0.67 cm- ) = 0.425; e-
= 0.65 ).
Since the gama dose rate at 6 feet from the cask surface (for the metallic fuel rods) under normal conditions was estimated as 0.54 mrem /hr, loss of the copper shield would increase this dose rate to 0.729 mrem /hr.
The applicant has estimated this dose rate conservatively to be 0.824 mrem /hr.
Since these estimates are well under the regulatory limit of 10 mrem /hr for normal conditions, the requirement of 10 CFR Part 71 will be met under both normal and accident conditions with or without the presence of the auxiliary shielding.
8 Cha es E. Mac ona d, Chief '
Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date:
R30W
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