ML19023A327

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Framatome Inc., Certificate of Compliance No. 9372
ML19023A327
Person / Time
Site: 07109372
Issue date: 01/23/2019
From: John Mckirgan
Spent Fuel Licensing Branch
To:
Framatome
Shared Package
ML19023A325 List:
References
TJT:19:004, USA/9372/B(U)F-96
Download: ML19023A327 (9)
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NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 1 2 71-9372 USA/9372/B(U)F-96 1 OF 9
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 Title 10, Code of Federal Regulations, Part 71, "Packaging and Transportatio*n 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) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Framatome, Inc. Framatome TN-81 Safety Analysis Report, FS1-2101 Horn Rapids Rd. 0014159, Revision No. 8, dated March 27, 2018.

Richland, WA 99354

4. CONDITIONS This certificate is conditional upon ful911ing the requirements of 10 CFR Part 71, as applicable, and the. '~nditions specified below.

5.

(a) Packaging (1) Model No.: TN-81 (2) Description -_-,i

~ *f ,' ~ ' / .: ,! ' ' \ ' ~ *., :./_,. J / //<;( -. J The Model No. TN-81 pa:c~age isi;:i .rectangular ~oXi j'l:'42 tl'Jt'i1 (:2,~:21 in)hjgh by 720 mm (28.35 in) wide by 5,068 mm (199.q3;.in) long, d~sigried fbt the trarispprt of unirrpdiated fuel assemblies or individual fu,~I rods with an ""enrichmeint up to .5:0 weight percent U-~35. The package carries a maximum of (i) two Boilin~)J\.l,9t:~t Reactor(B\Jy,~) fuel asi;H~mblies or ,Jn¢ividual rods, meeting the ASTM C996-96 st,andard of enrig_tied*9Ph1m-~r;cial grade ~*ranium, §!Jlriched reprocessed uranium, or (ii) uranium oxitj,13 generic pressurizeCl)N'a~~f-:;reactor (PWR) or l:.lfs;ihium carbide loose fuel rods in a 5 inch diameter stainless steel pipe.' !i, * ,

with residual contamination The package is comprised of one inner container and one outer container both made of stainless steel. The inner container has aaouble-wa[LstainlesE; steel sheet structure with an alumina silicate thermal insulator, filling the gap betweel'l the two walls, to reduce the flow of the heat into the contents in the, event of a fire. Foam polyethylene cushioning material is placed on the inside of the inner container for protection of the fuel assembly.

The outer container is comprised of a stainless steel angular framework covered with stainless steel plates. Inner container clamps are installed inside the outer container with damping devices to minimize vibrations during transport. Wood and honeycomb resin-impregnated kraft paper act as shock absorbers. The fuel rod clad and ceramic nature of the fuel pellets provide primary containment of the radioactive material.

NRC FORM 618 U.S. NUGLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 1 71-9372 USA/9372/B(U)F-96 2 OF 9 5.(a)(2) continued The approximate di.mensions and weights of the package are as follows:

Maximum gross shipping weight 1,614 kg (3,558 lbs)

Maximum weight of inner container 308 kg (679 lbs)

Maximum weight of outer container 622 kg (1,371 lbs)

Maximum weight of packaging 930 kg (2,050 lbs)

Dimensions of inner container Length 4,686 mm (184.49 in)

Width 459 mm (18.07 in)

  • Height 286 mm (11.26 in)

Dimensions of outer contafner Length '5;968 mm (199.53 in)

Width . 720 h:im (48.35 in)

. Height 742 mm (?c§,21 in)

,,/ .,

(3) Drawings This packagingJis constructed in accordancef\Nith the TN:::B~

~ ..... ,~

Drawing No§.:

Outer Conlainer Drawings .

105E37.37, Rev. 6 ,. . .

105E3738, .sheets 1 9..nd 2, Rev. '8 105E373-8; sheet3,.Rev. 7

  • 105E3739,...~Rev. 4 *.
  • 105E3740r Rev. 4 105E3741,\Rev. 1 *_/

105E3742, Rev~3 105E3743, R'ev; '5.

02-9162717, Rev,11 Inner. Container Drawings Co.ntents Containers 105E3745, sheets 1-4, Rev; 8 105E3773, Rev. 1 105E3746, Rev. 1 0028898, Rev. 1 105E3747, Rev. 4 105E37 48, Rev. 2 02-9162722, Rev. 1

NRG FORM 618 U.S. NUCLEAR RE'GULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 1 71-9372 USA/9372/B(U)F-96 3 OF 9
5. continued (b) Co.ntents

( 1)" Type and form of material Enriched commercial grade uranium or enriched reprocessed uranium, as defined in ASTM C996-96, uranium oxide or uranium carbide fuel rods enriched to no more than 5.0 weight percent U-235, with limits specified in Tables 1 and 2 below.

Table 1: Maximum weight of uranium dioxide pellets per fuel assembly

':3 Type 8x8 fuel ~ype 9x9 fuel Type 10~10 fuel Type 11 x11 fuel assembiy ' assembly assernbl'y assembly 235 kg 240 kg 275 kg 281 kg Table 2: Maximum Authorized Conc;entr~fi_dns

_Isotope Maxim1.~:m content

... )

I\

LJ.*232 2:00.<><'

10-9J g/gU i )'j -',>' '

x19 g/gU J .'.'

!:J-235 5.00

, , _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _'";,,.,..,..-1_, ,

, U-236 -2.50 X 10-2 g/gU

.':; //

5 I U-238 Balance of Uranium . ,, .,,,

Np-237 1.66 x 10-~ 9}9 u Pu".'238 6.2-Q x 10-11 g/gU Pu-239 3.04 x *10-9 g/gU Pu-240 3.04 x 10-9 g/gU Gamma 5.18.x 105 MeV-Emitters Bq/kgU Maximum content of U-238 is 9.23 x 10-19/gU for a maximum U-235 concentration of 5%. Since, for concentrations less than 5%, ttie U238 value will be higher, it is shown as "Balance of Uranium" in Table 2.

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

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER P.AGE PAGES 9372 1 71-9372 USA/93 72/B( U)F-96 4 OF 9 5.(b)(1) continued (i) 8 x 8 fuel assemblies comprised of 60 to 64 rods in a square array with a maximum active fuel rod length of 381 cm. The maximum pellet diameter, minimum clad thickness, rod pitch, water rod and poisori rod specifications are- in accordance with Table 3 below.

(ii) 9 x 9 fuel assemblies comprised of 72 to 81 rods in a square array with a maximum active fuel rod length of 381 cm. The maximum pellet diameter, minimum clad thickness, rod pitch, water rod and poison rod specifications are in accordance with Table 3 below.

(iii) 10 x 10 fuel assemblies comprised of 91to100 rods in a square array with a maximum active fuel rod length of 385 cm. The, maximum pellet diameter, minimum clad thickness, rod pitch, water rod and poison rod specifications ar1;3 in accordance wJth Table 3 below.

> \

(iv) 11 x 11 fuel assemblies c:;omprised of 112 rods in a square array with a maximum active fuel rod length of 385 cm. The maximum pellet diameter, minimyrxi clad thickness, rod pitch, water rod and .poison rod specifications are in accordance with Table 4 below.

(v) Uranium oxide fuel:rods configured loose, in a 5 inch diameter schedule 40 stainless steel pipe/prote,ctiV.e case or str'%pped together. When fuel r~qfare pl~c§"9 in polyethylene sleeves, ea¢h polyethylene sleeve shall not excE?e'd 0.0152 cm in thickness. The maximum pellet diameter, minimum clad thickress, ~r,id rod spedflcations are in accordance with Table 5 below. * *  ;

< ' . .1 (vi) Uranium carbide or, generic PWRuranium bxidefuerfods qonfigured loose, in a 5 inch diameter ~cheddle 4d
stainless steel pipe.. When. fyel' ro~.~ *.~.re placed in polyethylene sleeves, each polyethylE:me slel¢Ye shall not e~@e,ed o.ql52 6m in thickness. The maximum pellet diameter, minimum clad thickness, and rod specifi69tibns are lh accordance with Table 5 below.
  • l~.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 1 71-9372 USN9372/B(U)F-96 5 OF 9 5.(b)(1) continued Table 3: Fuel Assembly Parameters (8x8, 9x9, 10x10)

Parameter Units Type Type Type Type Fuel Assembly Type Rods 8x8 9x9 FANP lOxlO GNF 10xl0 U02 Density  % :S98% :S98% S98% :S98%

Theoretical Theoretical Theoretical Theoretical Number of water rods* # 0,2x2 0, 2-2x2 0, 2-2x2 0, 2-2x2 off-center off-center off-center diagonal, 3x3 diagonal, 3x3 diagonal, 3x3 Number of fuel rods # 60- 64 n- 81 91 - 100 91 - 100 Fuel Rod OD cm 2: 1.176 2: 1.093 2: 1.000 2: 1.010 Fuel Pellet OD cm, ;Sl.Q5., .* :SO.Q,6 s0.895 S0.895 Cladding Type Zirconium Alloy Zirconium Alloy Zirconium Alloy Zirconium Alloy Cladding ID cm s 1.10 s 1.02

0.933 s 0.934 Cladding Thickness cm 2
0.038 2: 0.036 ' .* 2: 0.033 2: 0.038 Active fuel length cm S381 S385 Nominal Fuel Rod Pitch - cm 1.63 < 1 45

-~*

,;; ...,_ ; s 1:30_.

- 1.30 U-235 Pellet Enrichment ** * \

wt% .

S;5.0 ;S;5.0 Maximum Lattice Average ..

Enrichment wt% ;S;5;0 . ;S;5.0 Channel Thicknessh ** .. ... *cm . 0.11 --:.o:.so48 0.17-0.3048 0.17 :__ 0.3048

.. I Partial Length Fuel Rods; (113 through 2/3 normaUength) 14 .... 14 Gadolinia Requirements Lattice Average Enri~hmentc -#~ .,',' ,1., ' \' __;- "

S 5.0 wt% U-235 @,wt% 7@*2:wt% .* 10'@2wtY. ' >i2@2wt% .12@2wt%
S 4. 7 wt% U-235 ('Jd203 . ~@ 2 wt%' ' ' 8 @ 2 wt% ;'. / 12@ 2 wt% 12@2 wt%
S 4.6 wt% U-235 .6@'2 wt% .8 @2wt%' 10 @:2'"Wt% 10@2 wt%
S 4.3 wt% U-235 - *. * ***6.@?z:wt% **s.'@2wtfYo 9@2*.~t% 9@2wt%
S 4.2 wt% U-235 .6~_w;.i m~:*~>" 6 @2 wt%

8 iWi% 8@2wt%

_::: 4.1 wt% U-235 4@2wt%\~::

  • 6@2 W't% 3"@2 wt% 8@2wt%

_::: 3.9 wt% U-235 4@'.2Wt% 6@2wt% 1)@2 wt% 6@2wt%

_::: 3.8 wt% U-235 4 @ 2 \'vt% 4 @ 2 wt% . ', -6 @ 2 wt% 6@2wt%

.:S 3.7 wt% U-235 2 @ 2 wt% 4 @ 2 wt%\;< . 6 @ 2 wt% 6@2wt%

S 3.6 wt% U-235 2 @ 2 wt% 4 @ 2Vwt% ',* 4 @ 2 wt% 4@2wt%

_::: 3.5 wt% U-235 ~@.2wtY,,

  • 2*@Q...wt% 4@2wt% 4@2wt%

.:S 3.3 wt% U-235 2@fWi% . 2@2wt% 2@2wt% 2@2wt%

.:S 3.1 wt% U-235 None 2 @ 2 wt% 2 @ 2 wt% 2@2wt%

_::: 3.0 wt% U-235 None None 2@2wt% 2@2wt%

s 2.9 wt% U-235 None None None None Polyethylene Equivalent Massd (Maximum per Assembly) kg 11 11 10.2 10.2

a. For 8 x 8 fuel assembly designs, there can be either 0 or I water rod; the water rod location occupies a space equivalent to 2 x 2 fuel rods. This is designated as 0, 2 x 2 in the table, For 9 x 9 and 10 x 10 fuel assembly designs, there can be either 0, 1, or 2 water rods in the assembly; the water rod location occupies a space equivalent to (i) two 2 x 2 fuel rod*equivalent spaces on a diagonal at the center of the assembly, or (ii) one 3 x 3 fuel rod equivalent space (9 fuel rods space) in the center of the assembly.

These configurations are designated as 0, 2 - 2x2 off-center diagonal, 3x3 in the table.

b. Transport with or without channels is acceptable
c. Required gadolinia rods must be distributed symmetrically along the major diagonal.
d. Polyethylene equivalent mass calculation per Section 6.3.2.2 of the application,

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

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 1 71-9372 USA/93 72/B(U)F-96 6 OF 9 5.(b )( 1) continued Table 4: Fuel Assembly Parameters ( 11 x11)

Parameter Units Value Fuel Assembly Type Rods l lxl 1 U02 Density* g/cm3 Sl0.763 Number of water rods # 3x3 center Number of fuel rods # ll2 Fuel rod OD cm 2:0.930 Fuel Pellet OD cm S0.820 Cladding Type Zirconium Alloy Cladding ID cm .:.:_1 S0.840 Cladding Thickness .* cm " 2:0.045 Equivalent Nominal Ftiel Rod Pitch cm  :'=;l.195 U-235 Pellet Enrich~ent wt% <S.O T

Maximum L~lfic,e Average Enrichment wt% S5J)

Fuel Channei'Side-Thicknessh

. } "
>*. . ,

cm ,,,~0.~54 Full Length Fuel Rods Quantity # 92 Active Length cm S385 Short Part Length Fuel Rods .

.Quantity # 12 Active Length cm Sl55.l Long Part Length Fuel Rods ,_ ~

  • Quantity # . :.. 8' '

Active Length: cm '. :5?~~6.8 Gadolinia RequirementsLattice . ,. ,...

Average Enrichment" S 5.0 wt% U~235 \,; 13 @2 "'.!.% .*

I S 4.8 wt% Uc235 12@2 wt.%

s 4.6 wt% U-~i\S . 11 @2~%

S 4.4 wt% U-235

  • i 10@2 wt%

S 4.2 wt% U-235

  • 9@2wt%

S 4.1 wt% U-235 .~@2wt%

S 3.9 wt% U-235 #@wt% 7@2wt%

S 3.8 wt% U-235 ' Gd203 .)'

6@2wt%

S 3.6 wt% U-235 5@2wt%

S 3.5 wt% U-235 4@2wt%.

S 3.3 wt% U-235 3@2wt%

S 3.2 wt% U-235 2@2wt%

2.9 wt% U-235 None Polyethylene Equivalent Mass kg 10.2

!(Maximum per Assembly)d

a. Density based on a pellet modeled as a right cylinder

. b. Transport with or without channels is acceptable.

c. Required gadolinia rods must be distributed symmetrically along the major diagonal, and shall not be placed on the periphery.
d. Refer to Section 6.3.2.2 of the application.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (B-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 9372 1 71-9372 USA/9372/B(U)F-96 7 OF 9 5.(b)(1) continued Table 5: Fuel Rod Paramet$rs Parameter Units Type CANDU- CANDU-Fuel Assembly . 8x8 9x9 lOxlO llxll Generic 14 25 Type (U02) (U62) (U02) (U02) .PWR(U02)

(UC) (UC)

U02orUC g/cm3  ::.:10.14 sl0.74 :Sl0.74 Sl0.763 :S13.36 Sl3.36 Sl0.74 Fuel Density*

Fuel rod OD cm 2:1.10 2:1.02 2:1.00' 2:0.930 2:1.340  :.:o.996 2:1.118 Fuel Pellet OD cm Sl.05 ~0.96. so.9o :S01820 Sl.254 s0.950 so.98 Zirc. Alloy Zirc. Alloy Zirc. Alloy Cladding Type Zirc. Alloy Zirc. Alloy Zirc. Alloy Zirc. Alloy or'SS or SS or SS Cladding ID cm Sl.10 sI.02 Sl.00 .so.930 <l.267*

-*,.::._,,..' s0.951 Sl.004 Cladding cm :_:0.0.38 2:0.036 2:_0.038 20.045 ~~*-

-* ~0.033 2:0.033 2:0.033 Thickness /

" - __ , ~~

Active fuel Length cm <$81 S381 S385 6385 "o[;~* S47.752 S40.013 S450.

Maximum U-235 .,

wt.% . S5.0 S5.0 <5.0 s5.o } S5.0 S5.0 .::;5.0 Pellet Enrichment ~1.:,__.

)

i -

Maximum Average fuel rod wt.% :s5.0 S5.0 .. s5.0 s5.o S5.0 S5.0 S5.0 Enrichment . ,>>!

-  ; -'/.

Loose Rod ..

,l Configuration ..,

Freely Loose or "'

Strapped Together

  1. S25  ::;::25 S25 $5 NIA NIA NIA Packed in 5" SS

'" .. l Pipe or protective  :)

Case, i.e., SS Box

  1. S22 S26 ~o S30 S74b Sl30° S105b with Lid ' ~.

.il \ *.

a. Density based on a pellet modpled as a right cylinder. .
b. Including partial rods -using dense packing of congruent rods- in the 5" SS pipe

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 1 71-9372 USA/9372/B(U)F-96 8 OF 9 5.(b)(2) Maximum quantity of material per package Total weight of payload contents (fuel assemblies; or fuel rods, and rod shipping containers) not to exceed 684 kg (1508 pounds).

(i) For the contents described in 5(b)(1)(i), 5(b)(1)(ii), 5(b)(1)(iii), and 5(b)(1)(iv): two fuel assemblies. . *

(ii) For the contents described in 5(b)(1)(v) and 5(b)(1){vi): allowable number offuel rods per compartment (2 compartments per package).

(c) Criticality Safety Index, except for contents described in 5(b)(1)(vi) and limited in 5(b)(2)(li) ' 1.0 Criticality Safety Index for cq.ntents described in 5(b)(1)(vi) and limited in'5(b)(2)(ii)

  • 2.1
6. In addition to the requirements of Subpart G of 10 CFR Part 71:

(a) The package shall be prepared for shipment and operat~d in aCf?ordance wlth Chapter 7 of th.e application. *

(b) The packaging ml1st meet the Acceptance Tests and M,ainten?nce Program ,of Chapter 8 of the application. *

( c) Prior to ~ach shipment, the fuel rods shall conform 'to the leak te.sts .and specjfic inspection techniques used for qualificatibn ahd ih".process inspections as d~flhed in Chapter 8. Stainless steel components of the packaging must be visually ihspected. Packages in which stainless steel components show Ritting corrq'$ion; cracking, or pinholes, are hot authorized for transport.

-- ' < .~ ." --

    • - _._', . .t.\, . .,.;' .* '

(d) If ~rapping is used on the unirradiated fuel ai~yem'~lies, their ends mu~t be assured to be open dunng transport. * .* . * ** * .

7. All fuel to be shipped must meet the maximum P(r/t) criterion-product of the pre-pressure and of the maximum *Inside Radius/Thickness- of 10.18653 MPa .. Shipment of 11 x11 fuel designs manufactured by other suppliers than Framatome is not authorized. ATRIUM 11x11 fuel shall contain only commercial grade uranium, i.e., cannot be made from down-blended low enrichment fuel or reprocessed uranium.
8. Cluster separators are optional and may be comprised of polyethylene or other plastics. Polyethylene or plastic mass limits shall be determined in accordance with Section 6.3.2.2 (Material Specifications) of the application.
9. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
10. Transport by air of fissile material is not authorized.

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

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 1 71-9372 USA/93 72/B(U) F-96 9 OF 9 1
11. Revision No. O of this certificate may be used until April 30, 2019.
12. Expiration date: April 30, 2019.

REFERENCES Framatome TN-B1 Safety Analysis Report, FS1-0014159, Revision 8, dated March 27, 2018.

and supplemental information submitted on January 23, 2019 F THE U.S. r;9LEAR REGULATORY COMMISSION

/11-}

McKirgan, Chief nt Fuel Licensing ranch

Division of Spent Fuel Management Office of Nuclear Material $afe.fy * *.

  • and Safeguards *
  • Date: June<.J, 2018 TBD

.J

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