ML19346H897

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Enclosure 4 - Proposed Npc CoC Revision Mark-ups to Be Included in Revision 9 of the CoC
ML19346H897
Person / Time
Site: PROJ0712, 07109294, 99901376
Issue date: 05/22/2015
From: Michele Sampson
Global Nuclear Fuel, Spent Fuel Licensing Branch
To:
Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML19346H890 List:
References
M190194
Download: ML19346H897 (6)


Text

ENCLOSURE 4 M190194 Proposed NPC CoC Revision Mark-ups to be Included in Revision 9 of the CoC Non-Proprietary Information

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10CFR71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.
a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9294 g~

71-9294 USA/9294/ AF-96 1

OF

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2.

PREAMBLE

a. This certificate is issued to certify that the package (packaging and contents) described in Item 5 below meets the applicable safety standards set forth in Trtle 10, Code of Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."
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 applicable regulatory agencies, including the government of any country through or into which the package will be transported.
3.

THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION

a.

ISSUED TO (Name and Address)

Global Nuclear Fuel - Americas, LLC P.O. Box 780 Wilmington, NC 28402

b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Global Nuclear Fuel -Americas, LLC, application dated February 12, 2015December 18, 2019.

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4. CONDITIONS
5.

(a)

This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

Packaging 0

(1)

Model No.: NPC (2)

Description A cubic stainless steel and foam outer packaging with nine cylindrical containment vessels for the transport of type A quantities of low-enriched uranium oxide powder, pellets, and compounds of uranium as defined in 5(b ). The overall package dimensions are approximately 45 inches wide, 45 inches deep, and 44 inches high.

The outer packaging consists of a 10-gage stainless steel outer shell with a ceramic fiber board liner and rigid polyurethane foam filler. The foam filler has a three-by-three array of vertical cylindrical cutouts that accommodate stainless steel sleeves for placement of the containment vessels. The outer packaging is equipped with a top cover that is secured to the outer packaging body by a combination of 16 closure cap screws and four closure strips secured by 24 bolts.

The containment vessel is a maximum 8.515 inches in inner diameter and approximately 32 inches in overall length. The containment vessel is constructed of 18-gage stainless steel, surrounded by a cadmium sheet and polyethylene wrap within a 24-gage stainless steel jacket. The containment vessel is closed by a 16-gage closure lid, a silicone rubber gasket, and a band clamp assembly, which is composed of a 0.063-inch thick strap and retainer, a T-bolt, and a nut.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10CFR71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.
a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE 9294 g~

71 -9294 USA/9294/ AF-96 2

OF The gross weight of the package (packaging and contents) is 1,302 kg (2,870 pounds). The maximum weight of the contents is 540 kg (1,190 pounds).

5.(a)

(3)

Drawings The packaging is fabricated and assembled in accordance with the following Global Nuclear Fuel - Americas, LLC, Drawing Nos.:

(b)

Contents 177D4970, Sheet 1, Revision 1 177D4970, Sheet 2, Revision 0 177D4970, Sheet 3, Revision 0 177D4970, Sheet 4, Revision 0 177D4970, Sheet 5, Revision 0 177D4970, Sheet 6, Revision 0 177D4970, Sheet 7, Revision 0 177D4970, Sheet 8, Revision 1 SK105E4037, Sheet 2, Revision 1 Material Forms+

(<5.00 wt% U 235)

Restristion:

Homogenous Uranium Oxide/Compounds2 Heterogenous uo~ Pellets (BVVR)

Heterogenous uo~ Pellets(PVVR)

Heterogenous Uranium Compounds3 Minimum Qi;;>

(lnshes) f:.J+A

~

~

Unrestristed partisle sii!:e Maximum Loading Maximum Loading per ICC,6. (kgs) per N PC (kgs)

~ Uranium

~ Uranium

~

~ ~ 4-+Y

~

4-QM.

~ ~

~

4-QM.

~ ~

~

4-QM.

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+-No solutions or liquids are authorii!:ed and there shall be no free liquid present The Material Form within any NPC must be the same.

i_Homogenous sompounds limited to UO~~. U~. dried salsium sontaining sludges, U0;,(~~03)-2 el*bO, anel uranil
:1m oxiele eeariA!11 ash.

3-Heterogenous sompounds limited to uo~. U3~

Maximum sontent weight of any Inner Containment Canister Assemblies (ICCA) including plastic er secondary packaging (i.e., dunnage). Materials,,...,itl=I a l=lydregen atom density greater tl=lan PAGES

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NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10CFR71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.
a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE 9294 g~

71-9294 USA/9294/ AF-96 3

OF that of water are liFRited to a FRass of J.7 kg per ICCA. Table 1 - Type, Form, and Maximum Quantity of Material Per Package Max. loading per Max. loading per Material Forms-i-Particle Size ICCA (ka)

NPC (ka\\

(<5.00 wt.% U-235}

Restriction Minimum Net4 u

Net4 u

OD (inches\\

Homogeneous Uranium~

NIA 60.0 52.89 540.0 476.0 Comnounds;!

Heterogeneous UOi 0.342 60.0 4G.a448.

540.0 Je4.S436.

Pellets (BWR) 48 3

Heterogeneous UOi 0.300 60.0 4G.a446.

540.0 Je4J~420.

Pellets (PWR) 71 4

Heterogeneous Unrestricted Particle 60.0 40.54 540.0 364.8 Uranium Comoounds3 Size

+ No soluUons or liquids are authorized and there shall be no free liquid present. The Material Form within any NPC must be the same.

1 l-lemegeneeus sempet,,1nels limiteel te UO@, U~~. elrieel salsium sentaining sluelges, uranyl nitrate (U~J}. uranyl nitrate he*ahyelrate (U~JH), uranium tetrafluoride (Ur4) 1 sodium uranate, sodium diuranate, dried (sodium sontaining) sludges, ammonium diurante (ADU), ammonium uranyl sarbonate (AUG), uranium O*ide bearing ash, and other solid uranium compounds with a percent uranium content less than theoretical u9rr 3 Heterogeneous compounds limited to UO~~~~

4 Ma*imum content weight of any ICCA including plastic receptacles (e.g., bags, bottles, etc.).

The material form column in Table 1 includes both homogeneous and heterogeneous uranium compounds in the form of dry solids resulting from scrap recovery processes and combustible waste incineration.

Compounds include (but not restricted to):

uranium oxides (UOi, U30 a, or UOx X>ll uranyl nitrate (UN, UOi(N03h) uranyl nitrate hexahydrate (UNH, U06(N03h*6HiO}

uranium tetrafluoride (UF4) sodium uranate (Na6U04) sodium diuranate (Na6U60 1) sodium diuranate hexahydrate (NaiUi01*6HiO}

ammonium diuranate (ADU, 3U03*2NH3*4H60) ammonium uranyl carbonate (AUC, (NH4)4*UOi*{C03h) dried calcium (Ca) containing uranium compound/mixture/sludge/ash, such as CaU03. CaU04, CaiUOs, Ca6U04, Ca3U06, CaU30 10*4HiO, CaU60 19*11 HiO and CaU6019*1 OHiO dried sodium (Na) containing uranium compound/mixture/sludge/ash, such as Na6U601*3Hi0 and Na,U,Oz*H,O dried iron (Fe) containing uranium compound/mixture/sludge/ash PAGES

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NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10CFR71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.
a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE 9294 g~

71 -9294 USA/9294/ AF-96 4

OF The material form column in Table 1 must comply with the following constraints:

Solutions and/or liquids are not authorized and there shall not be free liquid present. The solid form material within any individual NPC must be the same. Authorized uranium compounds may be mixed with other non-fissionable diluent materials (such as sand, iron, iron hydroxide, silica, carbon from ash. etc.) except for deuterium. tritium and beryllium. Materials such as uranium metal and uranium metal alloys are not authorized.

Homogeneous/heterogeneous uranium materials are limited to solid form with a uranium weight fraction (UFACT} less than or equal to U02 (UFACT < 0.88144} at theorical density(< 10.96 glee}.

For purposes of the homogenous to heterogeneous transition: if the particle size distribution is such that a majority of the particles are 1730 um or greater, then the unrestricted particle size payload of Table 1 applies. If a majority of the particle size distribution is below 1730 µm, the homogenous payload of Table 1 remains valid.

The maximum content mass of any ICCA inner packaging materials (e.g., HOPE/LOPE plastic bags or bottles) is unrestricted provided the mean hydrogen atom density of the material contents to be shipped inside the inner volume of each ICCA is not greater than water (< 6.6734e-02 atoms/b-cm). This limit is applied as an average hydrogen density of the entire content mass (uranium compounds and packaging materials) over the fixed inside volume of each ICCA..,.

Authorized materials also include U02 pellets present in standard BWR and PWR reactor fuel assembly lattice designs (e.g., PWR: 17X17: BWR: 10X10. 9X9. 8X8 nuclear fuel assemblies).

The payload within an NPC may be distributed in any ratio within the nine ICCAs, provided that the content of any one ICCA never exceeds 132.2 pounds (60 kg). and the maximum uranium payload of Table 1 are met. Within an ICCA the payload can be enclosed in plastic poly bottle receptacles (e.g., bags, poly bottles, etc.).

5.(c)

Criticality Safety Index 0.7

6.

In addition to the requirements of Subpart G of 1 O CFR Part 71:

(a)

The package must be prepared for shipment and operated in accordance with the Operating Procedures in Chapter 7 of the application, as supplemented. Within each ICCA, the contents and secondary packaging (i.e., dunnage) must provide a snug fit. The payload may be enclosed in plastic receptacles (e.g., bags, bottles, etc.). For payloads in plastic bottles, empty bottles may be used to minimize movement of the bottles within the ICCA.

(b)

Each packaging must be acceptance tested and maintained in accordance with the Acceptance Tests and Maintenance Program in Chapter 8 of the application.

7.

The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.

PAGES

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NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10CFR71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.
a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE 9294 g~

71 -9294 USA/9294/ AF-96 5

8.

Transport by air of fissile material is not authorized.

9.

Revision No. e-§..of this certificate may be used until November 30, 2015.

10.

Expiration date: November 30, 2020,.

REFERENCES Global Nuclear Fuel - Americas, LLC, application dated February 12, 2015December 18, 2019.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION Date: May 22, 201 I-

/RA/

Michele Sampson, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards PAGES OF

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