ML20203G663

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Certificate of Compliance 9086,rev 17,for Model HN-190-1 Package
ML20203G663
Person / Time
Site: 07109086
Issue date: 12/08/1997
From: Chappell C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20203G654 List:
References
NUDOCS 9712180182
Download: ML20203G663 (5)
v • d • e


Text

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- l p Nac ronu sis ............................gl U.s. NUCLEAR RCULATORY COMMIS$60N g '

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g " C" " CERTIFICATE OF COMPLIANCE g

i FOR RADIDAC11VE MAN.1ALS PACKAGES a i a 01RTinC ATI Ntutt R 6 kty:StoN Ntusui e pAcm,Act 3Dt.NTintATioN NtNBER g d FAGE NtubtR e TOTAt Ntwer.R Pacts g

> 9086 . 17 USA /9086/A 1 4 l g h 2 PRLAMati U h a Tins cerurame 16 inued to cemfy that the packages arid contents dewnted to item $ telow, neets ow artNat4e safet) staridards set fonh in Title 10. U ,

  1. Code 4i ' ederal Regulations. Pari 71.
  • Packaging and Transpnt. anon of Radioacthe Maienal
  • I j tt T1us cemrecme dies noi tehewe os consigare frorn comphance with any eequirement of the reguleuons of the U.s. Depanment of Transportanon ce caher U:

h aftigable regulatory agencies, including the gesemnwn: v.'any country through cr imo whnh the pacLage uill tw transported N 3 THil CI RTint ATI 15155t1D ON THE D A511 OF A S AFTTY AN ALY515 RIM)RT OF THE FACKAOL DtsiON OR APPUC ATION j e 1$5tTD 70(Asw mV Aprasi 6 TIT 11 ANDIDENTinCAT10N OF REPORT.,A APPUCAT10N N

' E 9' Molten Metal Technology, Inc. Safety Analysis Report for the HN-190-1 p' g ,

e 1009 Commerce Park Drive Radwaste Shipping Cask STD-R-02-006 g ,

, Oak Ridge, TN 37830 Revision 4. ,

e DOCKrfNtHBLR 71-9086 l

$g 4 CONDITIONS g

( This teruricaie is cand i orial upon fuirilhng the requirer wnis of 10 CTR Part 71, en apphcable, and its condition, s;ecir,ed telow. g

  1. 4 5 I h(a) Packaging l

(1) Model No.: HN-190-1 l

(2) Description l

. A steel encased, lead shield.d cask for radioactive material. The cask is E

  • I a right circular cylinder 82.5 inches high by 81.5 inches in diameter. The d
  • i cask cavity is 74.5 inches high by 75.63 inches in diameter. The cask side d I

h wall consists of a 3/8-inch taick inner steel shell, a 1-3/4-inch lead I h shell, and a 7/8-inch thick outer steel shell. The base is a 4-inch thick I h steel plate which is welded to the inner and outer steel shells of the side d

, h wall. A steel flange is welded to the inner and outer steel shells of the I side wall at the top. The lid is a 4-inch thick steel plate which is E

  • h t stepped to mate with the steel flange. The cask closure is sealed by a N d Viton or Buna-H 0-ring gasket located between the lid and steel flange. I
  • ii Positive lid closure is accomplished by thirty,1-inch studs and nuts. The a

% lid contains a centrally located 4-inch stepped steel shield plug. The d

% shield phg is sealed by a Viton or Buna-N 0-ring gasket, and sixteen,1/2- E i inch studs and nuts are used to provide positive closure. I

% 4 h Tie-down is accomplished by four-tie down lugs welded to the cask body. N h There are three cask lifting lugs, three lid lifting lugs, and one shield q l

% plug lifting lug. The package gross weight is 50,000 pounds, e

$ d ,

% (3) Drawings q

% I h The packaging is constructed in accordance with Hittman Nuclear & q l h Development Corporation Drawing Nos. STD-02-028, Revision 9; g

h STD-02-029, Revision 6; and STD-02-030, Revision 5. q
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Page 2 '- Certificate No. 9086 - Revision No.17 - Docket No. 71-9086 E.

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+ (b) Contents E;

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+ (1) Type and form of material (l

4', E Process solids either dewatered, solid or solidified, in secondary g

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+ containers, and limited to the following: (l

+'- Materials in which the radioactivity is essentially uniformly E

4 (1) g

/ distributed and in which the estimated average concentration g

+! per gram of contents does not exceed: q 0,0001 millicurie of radionuclides for which the A quantity in l

+ Appendix A of 10 CFR Part 71 is not more than 0.05, curie; y

+l 0.005 millicurie of radionuclides for which the A quantity in E

.I y

? Appendix A of 10 CFR Part 71 is more than 0.05 cu,rie, but not

,I more than 1 curie; or ( -

g il 0.3 millicurie of radionuclides for which the A, quantity in g Appendix A of 10 CFR Part 71 is more than I curie.

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lI (ii) Objects of nonradioactive material externally contaminated with l

g radioactive material, provided that the radioactive material is a not readily dispersible and the surface contamination, when gl averaged over an area of I square meter, does not exceed E g{I 0.0001 millicurie (220,000 disintegrations per minute) per El 21 square centimeter of radionuclides for whic1 the A quantity in E li Appendix A of 10 CFR Part 71 is not more than 0.05, curie, or 4

[1 0.001 millicurie (2,200,000 disintegrations per minute) per  %

square centimeter for other radionuclides.

I (2) Maximum quantity of material per package

[i Greater than Type A quantity of radioactive material with the weight of E ,

t the contents, ser.ondary containers and shoring not exceeding 14,500 W

?i pounds except the weight of the contents in HN-100 Series 1 Unit 5 El

'i must not exceed 6,900 pounds. Internal decay heat must not exceed 7  %

'a thermal watts. E

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h; Page 3'- Certificate No. 9086 - Revision No. 17 - Docket No. 71-9086 [

  • 1 4

)6. (a) for any package containing water and/or organic substances which could p

g radiolytically generate combustible gases, determination must be made by tests and measurements or by analysis of a representative package such that

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o the following criteria are met over a period of time that is twice the 4 E

li expected shipment time:

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3

[i (1) The hydrogen generated must be limited to a molar quantity that would (

p be no more than 5% by volume (or equivalent limits for other E p inflammable gases) of the secondary container gas void if present at E a STP (i.e., no more than 0.063 g-moles /ft) at 14.7 psia and 70* F); or #

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$; (2) The secondary container and cask cavity must be inerted with a diluent 6 fi to assure that oxygen must be limited to 5% by volume in those portions E

?i of the package which could have hydrogen preater than 5%. E E

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% for any package delivered to a carrier for transport, the secondary E

$ container must be prepared for shipment in the same manner in which W ,

+i determination for gas generation is made. Shipment period begins when E 5 the package is prepared (sealed) and must be completed within twice the E l t, expected shipment time. E E

f;i (b) for any package shipped within 10 days of preparation, or within 10 days E

% after venting of drums or other secondary containers, the determination in E

+ (a) above need not be made, and the time restriction in (a) above does not E

  • y, apply. g E

+i Except for close fitting contents, shoring must be placed between secondary (

+,, 7 . containers and the cask cavity to minimize movement during normal conditions of g!

+, transport. g E

3 The lid and shield plug lifting lugs must not be used for lifting the cask, and g g+, 8. shall be covered in transit. g

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9. In addition to the requirements of Subpart G of 10 CFR Part 71: (

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+, (a) Prior to each shipment, the packaging lid seals, if o>ened (or if security E

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+ seal is broken,), must be inspected. The seals must se replaced with new g seals if inspection shows any defects or every twelve (12) months, g whichever occurs first.

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(b) Each packaging must meet the Acceptance Tests and Maintenance Program of E

gl s' Section 8.0 of the application,

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(c) The package shall be prepared for shipment and operated in accordance with the Operating Procedures of Section 7.0 of the application. fg

10. The package authorized by this certificate must be transported on a motor vehicle, railroad car, aircraft, inland watercraft, or hold on deck of a seagoing l

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+l vessel assigned for the sole use of the licensee, fe 5

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Page 4 - Certificate No. 9086 - Revision No. 17 - Docket No. 71-9086 f b El

[i 11.

si The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 671.12. (g

12. Expiration date: April 1, 1999. This certificate is not renewable.

+i E Il' REFERENCES E

E h, E 8

-i Scientific Ecology Group, Inc. application dated May 18, 1993. E

[;Supplementsdated:June 23, 1993 and October 10, 1997.

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% FOR THE U.S. NUCLEAR REGULATORY COMMISSION E

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+i Cass R. Chappell, Chief E ti' Package Certification Section E' Spent fuel Project Office d s, Office of Nuclear Material Safety E '

y,i and Safeguards d i E

% Date: December 8, 1997 E E

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.  ; ,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30H64001 o%.,*..**/

APPROVAL RECORD ,

Model No. HN-190-1 Certificate of Compliance No. 9086 Revision No. 17 By letter dated October 10, 1997, Scientific Ecology Group, Inc., and Molten Metal Technology, Inc., requested that the certificate holder for Certificate of Compliance No. 9086 for the Model No. HN-190-1 package be changed from Scientific Ecology Group, Inc., to Molten Metal Technology, Inc. Molten Metal Technology, Inc., has accepted responsibility for the completeness and accuracy of the statements and representations of the previous certificate holder. Molten Metal Technology, Inc., will be responsible for maintenance of the certificate, the safety analysis report for the package design, and the quality assurance records in accordance with 10 CFR 671.91(c). Molten Metal Technology, Inc., stated that the records required by 10 CFR 571.91(c) for the package design will be maintained at their document control center in Oak Ridge, Tennessee. Molten Metal Technology, Inc., has been issued Quality Assurance Program Approval for Radioactive Material Packages No. 0870, under Subpart H of 10 CFR Pact 71.

The Certificate has been revised to show Holten Metal Technology, Inc., as certificate holder. These changes do not affect the ability of the package to meet the requirements of 10 CFR Part 71.

M4 Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date: December 8, 1997 l

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