ML20203H536

Certificate of Compliance 9222,rev 6,for Model 14-215 Package

ML20203H536
Person / Time
Site:	07109222
Issue date:	12/08/1997
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20203H517	List: ML20203H512 ML20203H536
References
NUDOCS 9712180423
Download: ML20203H536 (5)

Text

_ . .

f w w w w w w w w w w w w w w w w w w w=w w w w w n s w w w w w w;nis w w w w w w w w w w w

'5 CERTIFICATE OF COMPLIANCE I FOR RADIOACTIVE mTERIALS PACKAGES U

.6 " "'

i a CLR n n CATI Nt'M BER b RIVISION NUMBER c. PACF. AGE IDENTinC ATION NUMBER d PAGE NUMBER e TOT AL Nt'MBER PAGES

1. l 9222 6 USA /9222/A 1 4 l h h 2 PRLAMBLE N

$ a This cemfgate is issieed to cemfy that the packagmg and contents desenbed in hem 5 belos, rnects the apphcable safety standards set forth in Title : 0, U; 1

h Code of Federal Regulations, Pan 71, *Peckaging and Transpananon of Radioactive Matenal * !l b This cemreate does not reheve the consignor from comphance with any requirement of the regulauons of the U.s Department of Transpanation or other N fl g apphcable regulator) agencies. including the government of any country through or into which the package mill be transponed. E

?, 3 T1115 CLR*1nC ATill155VED a IssetDTO,w.aw m ON T)E B A$15 6OF mu A AND $ AFTTY :DcunnCAnON AN.*LY515 REPORT OF RtPoRT OF T1E PACLAGE DEstGN OR APPL OR APPucAnos I- CATION e d 4

Molten Metal Technology, Inc. Hittman Nuclear application dated g g! 1009 Commerce Park Drive December 14, 1987, as supplemented, y pl Oak Ridge, TN 37830 g h 71-9222

.. ooc,xTuuMBtR l

4 4 CONDmONS g

$ This cemf.cate is conditional upo.: fulfilhng the requirements of 10 CT1t Part 7 t, as applicable, and the conditions specified below, g

1. S. g

• i (a) Packaging I

q g (1) Model No.: 14-215 l

(2) Description l It Steel encased lead shielded cask for radioactive material. The cask is a I

't right circular cylinder with a 77.25-inch ID by 80.25-inch IH cavity. The I h outside diameter of the cask is 83.5 inches with a 92.25-inch height. The d

$i walls of the cask contain a lead thickness of 1.88 inches encased in d

'i 0.38-inch thick inner steel shell and 0.88-inch thick outer steel shell. The I b top cover and cask bottom are made up of two steel plates with thickness of I El 2.0 inches. The primary cask lid is secured to the cylindrical cask body by a h eight, 1-1/4-inch rachet binders. A secondary lid is centered in the primary E

1. j lid and is secured to the primary lid with eight, 3/4-inch studs and nuts. I h Each lid is provided with a Neoprene gasket seal. The cask is provided with I s a 12-gauge stainless steel liner (seal welded along all edges), a lid vent E 4 i

'I line with pipe plug, and a 3/4-inch drain line and pipe plug. The cask is a si p.ovided with four equally spaced lifting / tie-down devices. The primary lid I h is provided with three lifting lugs and the secondary lid is provided with I

% one lifting lug. The cask gross weight is 58,400 pounds. E

1. I

%, (3) Drawings I

% 5

!; The package is fabricated in accordance with Scientific Ecology Group, Inc. E S

i Drawing No. STD-02-077, Sheets 1 and 2, Rev. 11. I h I

% The optional shield inserts are fabricated in accordance with Scientific d

$ Ecology Group, Inc. Drawing No. STD-0?-086, Rev. O. a h I h d h a h 5

% 5

% d 4, g

( 9712100423 971200 I 4

PDR ADOCK 07109222 C PDR 5 ;

N dl i

!sorn s ,1, , , A , , , ,rrasam,,,,,,,,,,,m,,,,,,,,,,,,,,,,d

,.uwwwwww.wwwww.wwwwwww wwwwww.wwww .,ww.w...,

, p{Na,c, FORMS:eA cosemossu -o u.s. NUCLEAR RE2U'.ATORY COMMC$lON g!

l b n' 8,, Page 2 - Certificate No. 9222 - Revision No. 6 - Docket No. 71-9222 g

1. d i

1. ( I I

1. l 4,

S. (b) Contents a E

W, (1) Type and form of material a I

1. l

$ Dewatered, solids, or solidified waste, or activated solid components, p 9, in secondary containers, and limited to the following: q I

1. l g (i) Materials in which the radioactivity is essentially uniformly a distributed and in which the estimated average concentration per g

(#l gram of contents does not exceed: y

1. 1 g (I 0.0001 millicurie of radionuclides for which the A quantC.y in g Appendix A of 10 CFR Part 71 is not more than 0.05,curte; g

({

1

1. ' O.005 millicurie of radionuclides for which the A, quantity in

,! g

,l Appendix A of 10 CFR Part 71 is more than 0.05 curie, but not more g g than I curie; or g 0.3 millicurie of radionuclides for which the A, quantity in I ji g 4

Appendix A of 10 CFR Part 71 is more than 1 curie. g fi (ii) Objects of nonredioactive material externally contaminated with l 1 radioactive material, provided that the radioactive material is not 4

readily dispersible and the surface contamination, when averaged I

,I

,I over an area of I square meter, does not exceed 0.0001 millicurie U (220,000 disintegrations per minute) per square centimeter of I

,i I

.I radionuclides for which the A, quantity in Appendix A of 6 10 CFR Part 71 is not more than 0.05 curie, or 0.001 millicurie U Ti (2,200,000 disintegrations per minute) per square centimeter for U other radionuclides.

(2) Maximum quantity of material per package U Y

i Greater than Type A quantity of radioactive materia. which may contain U fi fissile material provided that the fissile material does not exceed the U

!i limits in 10 CFR 571.18 and $71.22. The decay heat load is limited to I

?i 9 watts, d

'i d Il$ I i E

1. i i

1. d 6

6 I

1. 5 i

1. 4 i

1. 4 0

1. E i

1. N i

1. E i

1. i 4 h I

% a

1. i- E

% a e E l t

. m_m_m m a a e m + = 2 m m a a a a m m e , af , a a a m , , d

,u_m=wuwwwwwwwwwwwwwwwwwww.ww.www.w.wwww. .wwwwg g NRC ORM $14A CONDmoN5 (conswfi U.S. NUCLEAR RE!ULATORY COMMISSION g l

j g{Page3-CertificateNo.9222-RevisionNo.6-DocketNo. 71-9222 g I *; N E

W d y 6. (a) For any package containing water and/or organic substances which could g g radiolytically generate combustible gases, determination must be made by (

p i

tests and measurements or by analysis of a representative package such that j g

i the following criteria are met over a period of time that is twice the g g

l expected shipment time: q hi (1) The hydrogen generated must be limited to a molar quantity that would be g

6 no more than 5% by volume (or equivalent limits for other inflammable f, 9 gases) of the secondary coptainer gas void if present at STP (i.e., no g g

i more than 0.063 g-moles /ft at 14.7 psia and 70'F); or g (2) The secondary container and cask cavity must be inerted with a diluent I

!i I ji to assure that oxygen must be limited to 5% by volume in those portions of the package which could have hydrogen greater than 5%.

l l For any package delivered to a carrier for transport, the secondary container U lJ must be prepared for shipment in the same manner in which determination for E 8

Ti gas generation is made. Shipment acriod begins when the package is prepared

'I (sealed) and must be completed wit 1in twice the expected shipment time.

!! (b) For any package shippu within 10 days of preparation, or within 10 days E Ti after venting of drums or other secondary containers, the determination in U

?i (a) above need not be made, and the time restriction in (a) above does not E apply. N S

i 7. Maximum gross weight of the contents, secondary containers, shield inserts and I ti shoring d.s limited to 20,000 pounds. E

'i E

$i 8. Except for close fitting contents, shoring must be placed between secondary I fi containers and the cask cavity to minimize movement during normal conditions of d S

i transport. I

?! 8

? 9. The lid and shield plug lifting lugs must not be used for lifting the cask, and E

%; must be covered in transit. E 4 4 s, In addition to the requirements of Subpart G of 10 CFR Part 71:

i

10. E f E i

9; (a) Prior to each shipment, the packaging Neoprene lid seals must be inspected. W i

The seals must be replaced within twelve (12) months prior to shipment. E

1. Also, seals must be replaced with new seals if inspection shows any defects. I s!i Cavity drain and vent lines must be sealed with appropriate sealant applied q E, to the pipe plug threads. g

'iD (b) The package shall be prepared for shipment and operated in accordance with W

q i

% the Operating Procedures of Section 7.0 of the application and Scientific C 9, Ecology Group, Inc. supplements dated May 16, 1990 and September 7, 1995. p

'i E b, (c) Each cask must meet the Acceptance Tests and Maintenance Program of Section ql

%, 8.0 of the application, as supplemented. In addition, the cask must be leak gl

% tested within twelve (12) months prior to shipment and each seal must be leak q!

% tested after replacement in accordance with Paragraph 8.1.3 of the ql t

i application, gl

$ hl <

h El l l

4, gl

_$m s m u m m m m mp m m m m m m m m an ims m_1 f m m m , m m m ,ty y, m m m y y m i m ,,c s E l

, wwwwwwwwwwwwwwwwwww.ww.wwww .www.wwww... . 1, p jFORM61BA ,

coNDmoNs uos ane U.S.NUCLEA3 CE!ULATORY COMM'2SION gl

1. , I tlPage4-CertificateNo.9222-RevisionNo.6-DocketNo. 71-9222 g 4, N 3

1. l11. The cask body and each lid must be marked in accordance with 10 CFR {71.85(c).

$ Nl g

E 9l12. The packages authorized by this certificate must be transported on a motor vehicle, railroad car, aircraft, inland watercraft, or hold or deck of a seagoing g-g

( vessel assigned for the sole use of the licensee.

1. l g E

1. l 13.Optional shield inserts may be used as needed. The optional shield inserts must be fabricated in accordance with Scie.itific Ecology Group, Inc., Drawing No.

g g

gl p STD-02-086, Revision O. g d

1. ' 14. The package authorized by this certificate is hereby approved for use under the e g

, general license provisions of 10 CFR 671.12. g N

i" .15. Expiration date: April 1, 1999. This certificate is not renewable, g si i REFERENCES si i Hittman Nutlear application dated December 14, 1987. l fHittmanNuclearsupplementsdated: January 26, March 25, and June 10, 1988. l h Scientific Ecology Group, Inc. supplements dated: April 3 and May 16, 1990; I I

si January 26, June 10, and October 4, 1993; February 3, February 25, and E

i March 2,1994; September 6,1995; and October 10, 1997. l a i

?i d N

?! FOR THE U.S. NUCLEAR REGULATORY COMMISSION U

It Tt n

?/ p

?i Cass R. Chappell, Chief 5

?i Package Certification Section W

?, Spent Fuel Project Office d

'i# Office of Nuclear Material Safety 8 i and Safeguards I b d S

t Date: December 8,1997 5

1. i i

?i i

?, d

't U i a s a

• i 8

'i 8

'i i a

1. d

'i t Il 4, g E a {l

'i i E

i El U

$r n ia; ,s m s m . m s , , , , , , ,m my , , , ,,, ,, ,y..

. . , , ,, , , , , , , , ,,F

• , , . p %g$#'r UNITED STATES p

• M,

! j NUCLEAR REGULATORY COMMISSION

'o WASHINGTON D.C. 20666 4 001 APPROVAL RECORD Model No.14-215 Certificate of Compliance No. 9222 Revision No. 6 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. 9222 for the Model No.14-215 package be charged 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. 0970, under Subpart H of 10 CFR Part 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.

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

- - . _ - - _ . _ - - . _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _