ML20211D425
| ML20211D425 | |
| Person / Time | |
|---|---|
| Site: | 07109176 |
| Issue date: | 09/17/1997 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20211D415 | List: |
| References | |
| NUDOCS 9709290131 | |
| Download: ML20211D425 (6) | |
Text
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a This certsfKate is 166ued to centfy that the pa Laging ud contents dencnted an item 5 telow, meets the apphcable safety standards set forth in Title 10,
$;j Code of Iederal Regulations. Part 71, *Patagir.g and Transportatma of Radunactne Matenal?
l b This certificate des ens reheve the c<e.signar frorn compharne with any requirement of the regulaimns of tiv U.s. Department of 'franspwtation sw other I;
appla able regulatory agencies, arnludmg the governrnent of any country through or into whnh the podere mill be transported N
3 Tills Ct R11nCAft 15155t'ID ON Till B A%110F A S Af1TY ANAL)515 kl. PORT Of Till PACAAGE DIAIGN OR APPLICATION k
a li$ULD 70 fNems and AM ful ti Tilli ANDIDLNT171 CATION Of RIPORT OR APPLICATION g
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Holten Metal Technology, Inc.
NUPAC application dated February 29, 1988, g
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1009 Commerce Park Drive as supplemented, y
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$, 4 CONDf11oNs 11us certifwate honditional upon fulfithrig the seguirements of 10 C)R Part 71, ei oppikable, and the conditons specified below g
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i (a)
Packaging l
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Model Nos.: NUPAC 14/210L, NUPAC 14/210H, CNSI 14-215H Series, A, LN 14-195L, I
I and LN 14-195H 4
4 (2)
Description l
'i Steel encased lead shielded casks for radioactive material.
The casks are d
- t right circular cylinders with a 77.25-inch ID by 80.25-inch IH cavity. The N
'i walls of the casks contain a lead thickness ranging from 1.25 to 1.88 inches N
8 encased in 0.38-inch thick inner steel shell and 0.88-inch thick outer steel I
1 shell. The top cover and cask bottom are made up of two steel plates with N
i8 thickness of 2.0 inches..The primary cask lid is secured to the cylindrical N
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cask body by eight, 1-1/4-inch rachet binders.
An optional secondary lid is d
e centered in the primary lid and is secured to the arimary lid with eight, I
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3/4-inch studs and nuts.
Each lid is provided wit 1 a Neoprene gasket seal.
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- j The casks may be provided with an optional 12 gauge stainless steel liner I
W (seal welded along all edges), an optional lid vent line with pipe plug, and a
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- i an optional 3/4-inch drain line with pipe plug.
The casks are provided with a
- j four equally spaced lifting / tie-down devices.
The primary lid is provided q
4, with three lifting lugs and the optional secondary lid is provided with one a
W lifting lug.
The casks gross weights range from 51,600 to 58,400 pounds.
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tj Model 00, Lead Tk, Top Tk, Bottom Tk, Gross Wt, q
9 Number ing.hu inches inches inches counds a
D;i NUPAC 14/210L, LN 14-195L 82.25 1.25 4.0 4.0 51,600 g
D, NUPAC 14/210H, LN 14-195H 83.5 1.88 4.0 4.0 58,400 g
b; CNSI 14-215H Series A 83.8 1.85 4.0 4.0 58,400 g
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Page 2 - Certificate No. 9176 - Revision No. 14 - Docket No. 71-9176 r
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(3) Drawing i
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D Model Nos. NUPAC 14/210L and NUPAC_ 14/210H i
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The packages are fabricated in accordance with Nuclear Packaging, Inc.,
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Drawing No. X-20-306-SNP, Sheets 1, 2 and 3, Revision No, A.
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Dj The packages may include an optional removable shield insert-fabricated g
Dp; in accordance with Pacific Nuclear Drawing Nos. PS-121892-1 and PS-121892 g
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submitted on December 21, 1992.
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Model No. CNS1 14-215H Series A r
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The package is fabricated in accordance with Chem-Nuclear Systems, Inc.,
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Drawing Nos. 24500-08, Sheets 1 and 2, Rev. D, and 24500s5, Rev. 2.
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p The package may include an optional removable shield insert fabricated in l
I accordance with Chem-Nuclear Systems, Inc., Drawing No. C-119-B-0017, p
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l Model Nos. LN 14-195L and LN 14-195H p
l lI The packages are fabricated in accordance with LN Technol,ogies
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D; Page 3 - Certificate No. 9176 - Revision No. 14 - Docket No. 71-9176 r
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5.
(b)
Contents i
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(1) Type and form of material i
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Dewatered, solid, or solidified waste, or activated solid components, in i
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secondary containers, and limited to the following:
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Matericls in which the radioactivity is essentially uniformly o
distributed and in which the estimated average concentration per i
gram of contents does not exceed:
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O.0001 mil 11 curie of radionuclides for which the A, quantity in g
of Appendix A of 10 CFR Part 71 is not more than 0.05 curie; t
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0.005 millicurie of radionuclides for which the A, quantity in i
l Appendix A of 10 CFR Part 71 is more than 0.05 curie, but not eI more than I curie; or Appendix A of 10 CFR Part 71 is more than -1 curie.uantit 0.3 millicurie of radionuclides for which the A q g
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Objects of nonradioactive material externally contaminated with l
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radioactive material, provided that the radioactive material is r
l not readily dispersible and the surface contamination, when I
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averaged over'an area of I square meter, does not exceed r
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0.0001 millicurie (220,000 disintegrations per minute) per square r
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centimeter of radionuclides for which the A quantity in g!
Appendix A of 10 CFR Part 71 is not more th,an 0.05 curie, or I-0.001 millicurie (2,200,000 disintegrations per minute) per I-
,i square centimeter for other radionuclides.
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(2) Maximum quantity of material per package r
h Greater than Type A quantity of radioactive material which may contain E
i fissile material provided the fissile material does not exceed the limits
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g in 10 CFR 671.53. The decay heat load is limited to 9 watts.
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Page 4 - Certificate No. 9176 - Revision No. 14 - Docket No. 71-9176 ul I
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6.
(a)
For any package containing water and/or organic substances which could a
e, radiolytically generate combustible gases, determination must be made by E
tests and measurements or by analysis of a representative package such that u
the following criteria are met over a period of time that is twice the a
4, expected shipment time:
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(1) The hydrogen generated must be limited to a molar quantity that would be g
no more than 5% by volume (or equivalent limits for other inflammable g
gases) of the secondary coptainer gas void if present at STP (i.e., no g
4 more than 0.063 g-moles /ft at 14.7 psia and 70*F); or a
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(2) The secondary container and cask cavity most be inerted with a diluent to a
assure that hydrogen must be limited to 5% by volume in those portions of g
4l the package which could have hydrogen greater than 5%.
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e' For any package delivered to a carrier for transport, the secondary container g
4 must be prepared for shipment in the same manner in which determination for g
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gas generation is made. Shipment )eriod begins when the package is prepared g
- g' (sealed) and must be completed wit 11n twice the expected shipment time.
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(b) for any package shipped within 10 days of preparation, or within 10 days y
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after venting of drums or other secondary containers, the determination in g
(a) above need not be made, and the time restriction in (a) above does not g
apply.
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7.
Maximum gross weight of the contents, secondary containers, shoring, and optional shield insert is limited to 20,000 pounds.
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8.
Except for close fitting contents, shoring must be placed between secondary 8
containers and the cask cavity to minimize movement during normal conditions of yl 8
transport.
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The lid and the shield plug lifting lugs must not be used for lifting the cask, and I
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must be covered in transit.
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- 10. The cask must be provided with either (or both) a drain line or a lid vent line as a
I shown in the drawing in order ta provide a method to leak test the package.
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N W, Page 5 - Certificate No. 9176 - Revision No. 14 - Docket No. 71-9176 g
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E In addition to the requirements of Subpart G of 10 CFR Part 71:
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>l (a)
Prior to each shiment, the packaging Neoprene lid seals if o)ened (or if i
4 security seal is aroken), must be inspected. The seals must ae replaced with q
D' new seals if inspection shows any defects or every twelve (12) months, which g
4 ever occur first. Cavity drain and vent lines must be sealed with a
$g' appropriate sealant applied to the pipe plug threads.
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(b)
Each packaging must meet the Acceptance Tests and Maintenance Program of:
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Model Nos. NUPAC 14/210L and NUPAC 14/210))
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Section 2.0 of the application.
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Model No. CNSI 14-215H Series A 4
Chem-Nuclear Systems, Inc., Document No. CNSI 9176-51, Rev. I', Section 4.0.
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Model Nos. LN 14-195L and LN 14-195H U
LN Technologies Corporation Procedures WM-036, Rev. A; WM-026, Rev. B; and I
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WM-013, Rev. F.
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(c)
The package shall be prepared for shipment and operated in accordance with the Operating Procedures of:
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I Model Nos. NUPAC 14/210L and NUPAC 14/210H d
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Section 7.0 of the application.
N tiodel No. CNSI 14-215H Series A E
Chem-Nuclear Systems, Inc., Document No.
CNSI 9176-S1, Rev.,1, Section 3.0.
ji Model Nos. LN 14-195L and LN 14-195H W
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LN Technologies Corporation Procedures WM-025, Rev. C.
- 12. The ratchet binders on the cask lid must be torqued to 100110 ft-lb.
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'i The cask body and each cask lid must be marked in accordance with 10 CFR 671.85(c).
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- 14. The packages authorized by this certificate must be transaorted on a motor vehicle, a
1 railroad car, aircraft, inland watercraft, or hold or dec( of a seagoing vessel d
assigned for the sole use of the licensee, u
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- 15. The packages authorized by this certificate are hereby approved for use under the N
general license provisions of 10 CFR 571.12.
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Expiration date: April 1, 1999.
This certificate is not renewable.
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>l Page 3 - Certificate No. 9145 - Revision No. 12 - Docket No.
71-9145 N
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(b) For any package shipped within 10 days of preparation, or within 10 days Nl W;
after venting of drums or other secoiidary containers, the determination in N:
(a) above need not be made, and the time restriction in (a) above does not E
p, apply.
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7.
Shoring must be placed between secondary containers (or activated components) and g
the cask cavity to prevent movement during normal conditions of transport, a
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l 8.
In addition to the requirements of Subpart G of 10 CFR Part 71:
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9' Prior to each shipment, the packaging lid seals must be inspected. The seals a
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(a) 4 must be replaced with new seals if inspection shows any defects or every 12 g
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months, whichever occurs first.
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e' Each package must meet the Acceptance Tests and Maintenance Program of g
p (b) p' Section 8.0 of the application.
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(c) The package shall be prepared for shipment and operated in accordance with g
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the operating procedures in Section 7.0 of the application.
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9.
The package authorized by this certificate must be transported on a vehicle, l
4' railroad car, aircraft, inland water craft, or hold or deck of a seagoing vessel g
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assigned for sole use of the licensee.
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i 10.
Lid lifting devices must be covered prior to transport to prevent their use as l
tie-down devices, y
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- 11. The cask body and each cask lid must be marked in accordance with 10 CFR 671.85(c).
l 8
- i
- 12. The package authorized for use by this certificate is hereby approved for use under the general license provisions of 10 CFR 971.12.
l l
13.
Expiration date: April 1, 1999.
This certificate is not renewable.
E
- l REFERENCH f
6
- 3 i
NVPAC Services Division, Inc. application dated February 21, 1991.
E W
i Supplements dated:
February 16, 1996 and August 5, 1997.
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FOR THE U.S. NVCLEAR REGULATORY COMMISSION 4
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a
- i Cass R. Chappe 1, Chief W
'l Package Certification Section Wl Spent Fuel Project Office NI i
9 Office of Nuclear Material Safety El and Safeguards El 9,
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4
- i Date: h t. 17. 1997 N
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NUCLEAR REGULATORY COMMIS810N -
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APPRO', AL RECORD Model Nos. NUPAC 14/210L, NUPAC 14/210H, CNSI 14-215H Series A, LN 14-195L, and LN 14-195H Certificate of Compliance No. 9176 Revision No. 14 By letter dated August 5, 1997, VECTRA Technologies, Inc., and Molten Metal Technology, Inc., requested that the certificate holder for Certificate of Compliance No. 9176 for the Model No. NUPAC 14/210L, NUPAC 14/210H, CNSI 14-215H Series A, LN 14-195L, and LN 14-195H packages be changed from VECTRA Technologies, 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 designs, and the quality assurance records in accordance with 10 CFR $71.91(c). Molten Metal Technology, Inc., stated that the records required by 10 CFR 671.91(c) for the package designs will be maintained at their document control center at 1556 Bear Creek Road, 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 Part 71.
The Certificate has been revised to show Molten Metal Technology, Inc., as certificate holder.
These changes do not affect the ability of the packages to meet the requirements of 10 CFR Part 71.
AM W'
Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date:
w. 17. 1997 m
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