ML20239A216

Summary of 980825 Meeting W/Nrc & Licensee in Rockville,Md Re Nuclear Fuel Svcs Uranyl Nitrate Tank Trailer Package

ML20239A216
Person / Time
Site:	07105059
Issue date:	08/27/1998
From:	Osgood N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9809080321
Download: ML20239A216 (1)

Text

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i UNITED STATES g

j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. - "1 e.,,,

August 27, 1998 MEMORANDUM TO:

Cass R. Chappell, Chief Package Certification Section, SFPO, NMSS FROM:

9 Nancy L. Osgood, Senior Project Manager Package Certification Section, SFPO, NMSS

SUBJECT:

MEETING

SUMMARY

REGARDING NFS URANYL NITRATE TANK TRAILER PACKAGE Attendees I

NRC.

NES Shaw Pittman Andrew Barto Tom Baer Phyllis Lorett Ross Chappell Rik Droke Wayne Hodges K. D. Hensley Hampton Newsome Patrick Koppel Nancy Osgood Neil J. Newman David Tiktinsky Bernie White introduction A meeting was held on August 25,1998, in Rockville, Maryland, at the request of Nuclear

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Fuel Services (NFS). The meeting was held to discuss the Model No. NFS Uranyl Nitrate Tank Trailer package (Certificate of Compliance No. 5059). The package is used for the 3

transport of bulk uranyl nitrate solutions. The meeting was held to discuss issues related to renewal of the Certificate of Compliance and to discuss the radioactive material authorized for transport in the package.

Discussion

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NRC presented a summary of the licensing background of the package. The package was initially approved by the AEC in 1965. The agency records do not include a staff Safety Evaluation Report that documents the basis for the approval. The package is grandfathered, and does not meet regulatory standards, since the package was not evaluated for cold temperatures, and could release radioactive material under normal conditions of transport, in addition, the criticality safety of the package is based on

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maintaining a suberitical concentration. However, conditions that could result in reconcentraHon or precipitation of the fissile material have not been systematically identified and evaluated. Such conditions could include extended cold temperatures, release of material and evaporation, and chemical reactions with fire fighting foams.

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9009000321 900827 PDR ADOCK 07105059

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NFS believed that uranium enriched to_five weight percent or less has an unlimited A 2

.value, regardless of whether the uranium is irradiated or unirradiated. NRC explained that the unlimited A value applies only to unirradiated uranium. Various isotopes present in 2

irradiated uranium must be considered when determining an A value. Typically, irradiated 2

uranium'is higher in U-234, which has a specific activity significant!y greater than U-235 and U 238. NRC presented background information on the transportation regulations, including the version of 10 CFR Part 71 that was superseded in April 1996, and IAEA

' regulations. These regulations showed that irradiated and unirradiated uranium typically have separate listings in the A tables, and that for irradiated uranium the A is calculated 2

2 for the mixture of radionuclides present. ' The attached meeting handout was provided by NRC. The meeting handout included the page from the safety analysis report for the NFS Uranyl Nitrate Tank Trailer package that specifies that the contents are unirradiated, and excerpts from various transportation regulations.

NRC is considering the NFS request for renewal of the Certificate of Compliance for the NFS Uranyl Nitrate Tank Trailer package. NRC is considering renew.ng the Certificate of Compliance with certain modifications. The modifications include clarifying that tiu uranium is unirradiated, and reducing the maximum allowable uranium enrichment of the contents to two weight percent. The letter that transmits the renewed Certificate would also include specific information that would be needed to increase the uranium enrichment back to five weight percent.

NFS requested that another meeting be scheduled in approximately two weeks to further discuss safety issues related to the NFS Uranyl Nitrate Tank Trailer.

Docket No.: 71-5059

Attachment:

As stated Distribution (w/ attachments: PUBLIC Docket File 71-5059 -

WFKane Distribution (w/out attachments:

NMSS r/f SFPO r/f Meeting Attendees Meeting Notebook Docket File 71-5059 BHWhite

'C" = Copy without attachment / enclosure

'E" = Copy with attachment / enclosure "N" = No copy oFC NMSS/SFPO E

NMSS/SFPO '

C NMSS/SFPO E

NLOsgood NERZiegler

'CRbphell NAME DATE 0 / 11/9 8

$/27/98 I/Z7/98 OFFICIAL RECORD COPY

[ygj 04TO RY oragym My.

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<NFS Nuclear Fuel Services, Inc. ERWIN, TENNESSEE 37650 (615) 743-9141 March 27, 1981 80 M ite g

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Mr. Charles E. MacDonald, Chief APR 0 71981 > [9 Transportation & Certification Brar h=

un Division of Fuel Cycle and Material 3

U. S. Nuclear Regulatory Commission th'"*

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Reference:

Docket 70-143; T,NM-124

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u Gentlemen:

of Certificate of Compliance No. 5059 for the NFS uranyl trailer.

No changes to the certificate have been requested in this appli-cation.

was submitted with the original request for renewal date 577t$

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The current certificate expires on April 30, 1981.

submission of application for renewal this existing license will not beSince this is a deemed to have expired until the application has been finally determined.

Very truly yours.

C C.

. Michel d

Administrative Manager CJM:kj Enclosure cc: Director, Region II (Meutt...

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CONSOLIDATED APPLICATION FOR RENEWAL OF CERTIFICATE OF COMPLIANCE FOR MODEL NO.:

NFS URANYL NITRATE TANK TRAILER Certificate No. 5059 Package Identification No.:

USA /5059/AF Submitted By:

Nuclear Fuel Services, Inc.

P. O. Box 218 Erwin, TN 37650 1

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n-Rev. 0 March 27, 1981 1.0 GE!!ERAL INFORMATION 1.1 Introduction This document represents a consolidated application for renewal of Certificate of Compliance No. 5059 for the Model No. Uranyl Nitrate Tank Trailer.

The package is used for the shipment of Uranyl Hitrate Hexa-I hydrate Solution.

The package is shipped Fissile Class II) and only one 1

l package is permitted per shipment.

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The applicable portions of tha format described in Regulatory Guide 7.9' l

" Standard Format and Content of Part 71 Applications for Approval of Packaging of lype B, Large-Quantity, and Fissile Radioactive P.aterial",

will be followed in this application.

1.2 Package Description 1.2.1 Packaging The weight of the tank trailer.is 14,000 pounds and it will carry up to 45,600 pounds of solution.

The tank trailer is constructed in accordance with DOT specifications MC-310, MC-311, or MC-312.

The 3,800 gallon insulated tank is of all 4

I welded construction.

The tank which is the containment vessel is 3/16 inch type 304 L stainless steel.

All welds are 100%

X-raycd.

The tank has no bottom outlets. The loading port is located on the top rear of the tank, and no other access to the tank is provided.

The tank is designed for operation at 35 PSIG.

The normal pressure in transit will be. essentially atmos-pheric.

Section 1.3 Appendix contains sketches of the tank.

1.2.2 Operational Features Water tight retainer pans have been provided underneath the full length of the tank to collect leakage that could occur under normal use.

A spill box is provided to contain leakage into the access port-during loading or unloading.

1.2.3 Contents of Packagina The package will contain Uranyl Nitrate in dilute acid solution.

The maximum U-235 enrichment in the uranium will not exceed 20%

by weight.

The U-235 content of the solution shall not exceed 10 grams per liter.

Since the Uranyl Nitrate is the final product of a facility which recovers unirrdiated low enriched uranium, no other. isotopes.aeerp'resentdn significant quantities.

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..The total uranium content shall not exceed 357 grams per liter.

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The nitric acid concentration wtll normally be_1.0M or less.

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1' 62 ANNEX!

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specific activity Syndpol Aaeosecude hp (C1/g)

U Uranism-238 m

3.33 x 10 '

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W Tangsans-181 W

4.98 x10 C g {,Q Q g3 8

Tungman:186 N

9.1 x10 j

8 Tungnan 181 W

1.0 x10 Xe Xenon 126(compseased or 8

encompremed)(ai m

1.39 x10 4

Xenon laim E

5.3 x10 Xenon 131m (decompressed)(a) y Xenon-133 m

1.96 x108 Xenon-133 (uncompressed)(a) yg Xenon-136 11 2.64 x108 Xence 136(uncompromed)(a) y T

Yttrie88 m

1.43 x 10' Yttrium 90 N

6.3 x10' Yttrium 91m m

4.11 x10'

2. 60 x 108 Tetriest m

Yttrium 92 N

9.6 x10' 8

Yttrium 93 N

1.24x10 8

Tb T erbium-176 N

1.18x10 In Zinc 66 W

B.2 x10s l

8 11ac-89m W

3.29 x10 11oc-69 N

6. 3 x 10' It Ziscontum-93 N

3.60 x 10*8 Zirconium 96 m

2.12 x 10' Zirconium-91 N

1.90 x108 (a) Uncompressed shall mean at a pressure not exceeding one atmosphew absolum at 0 C

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.C TABLE AHI-2. SPECIFIC ACTIVITY VALUES FOR URANIUM AT VARIOUS LEVELS OF ENRICHMENT Mass per cent of uranhun.235 SpeciSc activity' present in armanun snixture Bq/g Ci/g OSCr 1.s x 10*

s.0 x 10-'

0.45 0 ( r L.

2.6 x 10' 7.06 x 10*'

C S L' C 0.72 (natural) 2.s x 10' 7.6 x 10-'

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1.0 3.7 x 10*

1.0 x 10-*

b be 1.5 O (*t.: L N 1.0 x 10' 2.7 x 10-*

5.0 ggC( g 1.8 x 10' 4.8 x 10" b Q C L ((

10.0

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• 20.0 3.7 x 10 1.0 x 10~'

8 7.4 x 10' 2.0 x 10-s 35.0 9.3 x 10' 2.5 x 10-s 50.0 2.2 x 10' 5.3 x 10-s 90.0 2.6 x 10' 7.0 x 10-s 93.0 3.4 x 10' 9.1 x 10-s 95.0 i

• The values of the specific activity tactude the activity of uraniurn.234 which is concentrated dwing de

.n/J a..; process, and do int include any daughter product contribution. The values are ice de material originating from natural uranium ennched by a gaseous diffusion teethod. If the origin of the5 material is not known the specific activity should be either measured or calculated using isosopic sujo data.

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TAsLE A-1.-A AND As VALUES Fon RADIONUCUDEB-C0ritmutd

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tsee loomotes at and of ambie) 1

,%,3 symbolof remonuande Eismont and seemic nuneer A,qce A (ce m errameted)"

200n Themum(si) 30 30 s.sxir 300 300 12x10' l

301a 40 40 s.4 x 10' 303 300 10 4.3 x10' 304n 170m -

Thumum(es) 300 10 e.0 x10' 1000 100 1.1 x10' I

171em 330 Uranium (BE) 100 0.1 3.7 x10'

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30 OA3 L1x10

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233, 100 0.1 0.5 x10**

l 333 -

100 0.1 SJ x10-s j

334v 100 02 3.1 x 10**

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335, 300 02 S.3 x 10**

336, Unlimbed.

Unemned.

3.3 x 10*'

238v Unilmited.

Unlimited.

- ISEETABLE A-s(nonse0

Unemited, Untmited.

[SEE TABLE

<30%

4) 100 0.1 DBEE TABE A-20% or yester 4)

Unemmed.

Unemmed.

DBEE TABM A-

,(desioned) 4)

48, Vanadlum (33) 6 8

1.7 x10' 181a Tungsten (74) 300 100 8.0x 10' 1000 SS S.7 x 10* *

186, 40 30 7Ax10' 187o 70 70 18x10' 137s. (uncomposoodf Xenon (54) 5 5

EA x10' 137s. (compensedP 10 10 1.0 x10' 131mu (composeed)*

100 100 1Ax108 131m. (uncomposeed)'

1000 1000 12x10 s s

133 (uncomposeedP 5

5 1Ax10 e 133. (composeed)'

3 70 70 EJx10 8 135. (uncompresost0*

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136 (oomposeedr 87, Ytatum (30) 30 30 4.5x10 10 10 15x10

• 90, 30 30 4.1 x10 '

Sim, 30 30 15x10

• 91, 10 10 9.6x10 e 03, t,0 10 3Jx10 8 SS, 100n Yttertnum (70) 30 00 3.3x10 8 400 35 1 Ax10 8 17&n es.

Zine ;30) 30 30 s.0 x to

• 40 30 3.3 x10 e etmm 300 30 5.3 x10 '

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33 Zirconium (40) 1000 300 3.5 x10-s 30 30 11 x10

• 96, 30 30 10x10 e 97a

• For the purpose of Table A-1, compressed gas means a gas at a poseure which onceeds the amtment atmospherte prosaure at me loosson where the containment systern wee cioestL

" The values of A, and A, must be calculated in accordance with the procedure specified in Appendlx A. peregraph 11(3), taking into secount me activity of the fesion products and of the uranium-233 in addition to that of the thonum."* The values of As and A. mus me actMty of the fission products and plutonium isotopos in addition to that of the uranium.

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TAaLE A-f r-As AND Aa VALUES POR eymentcsemanmada

.Summe me mamme moeur A. free)

A. ga Am (7aq)

As 100 (Tagg) sows)

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s. trip hans sa s.it h10-8 tan,10-s sh10a ship has 82 8.11 b10-8 8.11:10-8 7 &10-s 21:10-s 4 50 8

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ham taeumme tamiend unenend Laenaud s h 10-*

t.t 10.

Th494 82 t ot 82 6A1 thip th10' htusse teemand taesend unsusend imenend Etate-o t h 10-'

lue Timmemmam sa tas 02 sat aA tJates mano Timmentet.1) es 21 4 sa 21 4 thw shw DW1 10 270 10 270 Thtr S.ts198 D8W K1 2

Kt Sht0' Eht9' 3M4 4

SW SS ISA 1J 198 4htes TaktS7 ftmanemp) 7 13 7

SW 3.tr198 Sh19' Tm. ten e2 -

$1s 62 sts s.tuw ske Tm t?O 4

ses SA 18A th19 th198 Ten 171 40 tu0 10 270 4h10' t.tr1F M 30 uistanM) #

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81.1 tr10-*

8.t ts te-s S h 10-8 th10s pas 10 270 tuto-s 2.70x10-s s h10-*

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thead 10 270 110-8 2.70m10-s t h 10-8 S h 10-s U.335 taesemd Laentud Laeseed Laenaud S h10-e R & te-*

O LAmt 10 270 1x10*s RJ0x10-8 t hit-*

S h 10-s n

U.338 L4ented taenauf usenaud unamand thtg-s get0-s g

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tag 84 113 thty ehtF be thebuhan640) 8 St.1 3

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Regulations for t.he Safe Transport of l

Radioactive Material 1996 Edition i

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No. ST-1 o i';,(g d ra NOM E ER Y AGENCY VIENNA 1

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ACTIVIIT IJMITS AND MATERIAL RESTRICTIONS TABLE 1.

(cont.)

Aedvity Acivity Radsonuclide (atosme number)

A; A

Activity Activity concentration limit for concentration limit for for enempt an enempt for exempt an exempt material consignment material consignment (Bq/g)

(Bq)

(TBq)

(TBq)

(Bg/g)

(Bq) i U-234 (slow lung 4 x 101 6 x 10-8 1 x 101 1 x 105 1 x 101 1 x 105 absorleonXO U-235 (alllung absorpuon Unlimited Unlimited I x 10 (b)

I x 108 (b) 1 1 x 101 1 x 106 tyPesXa),(d),(c),(O 1 x 102 1 x los U 236 (fast lung absorptionXd)

Unlimited Unlimited I x 10' 1 x 104 1 x 102 1 x 106 U-236(medium lung 4 x 108 2 x 10-2 1 x 102 1 x 105 1 x 104 1 x 104 absorpuonXe)

I U-236 (slow lung 4 x 10' 6 x 10-3 1 x 10' I x 108 1 x tr'*,

1 x 106 absorptionXO 1 103 1 x 106 U-238 (alllung absorpuon Unlimited Unlimited I x 10 (b) 1 x 10'(b) 8 l

1 x 108 1 x 108 87PesXd),(c),(O U (nat)

Unlimited Unlimited I x 10 (b) 1 x 10 (b) 0 3

1 5

1 x 10 (b)

I x 10 (b)

U (enriched to 20% or Unlimited Unlimited I x 100 3

,1 x 10 lessXg) 1 x 10' 1 x 10' U(dep)

Unlimited Ur. c :d I x 100 I x 103 Vanadium (23)

! x 101 1 x 10' V-48 4 x 10-8 4 x 10-3 1 x 10' 1 x 105 V-49 4 x 101 4 x 10' I x 108 1 x 107 0

5 I x 10 (b) 1 x 10 (b)

Tungsten (74) 1 x 108 1 x 104 W-178 (a) 9 x 100

$ x 100 1 x 10' 1 x 106 W 181 3 x 103 3 x 101 1 x 105 1 x 107 1 x 101 1 x 10*

W-185 4 x 101 8 x 10-3 1 x 108 1 x 107 1 x 101 1 x 104 W 187 2 x 100 6 x 10-8 1 x 102 1 x 108 1 x 102 3 x 305 W-188 (a) 4 x 10-3 3 x 10-3 1 x 102 1 x 108 Xenon (54)

I x 101 1 x 105 Xe-122 (a) 4 x 10-8 4 x 10-8 1 x 102 1 r.10' 1 x 101 1 x 10 Xe 123 2 x 100 4

7 x 10-1 1 x 102 1 x 10' 1 x 102 1 x 105 Xe 127 4 x 100 2 x 100 1 x IOS I x 105 i

Xe 131m 4 x 103 4 x 103 1 x 108

................................................1x108

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Forfootnotes see pages 36 and37.

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i ACTIVITY 1,DdTTS AND MATERIAL RESTRICTIONS Cs 137 Ba-137m Ce-134 la-134 ActMay ActMey Ce-144 Pr 144 canmanetton liant for Ba-140 14-140 for enseqpt an saampt Bi-212 71208 (0.36), Po 212 (0.64) maturnal enam8=nane Pb-210 B1-210, Po 210 Pb-212 (Bpg)

(Bal)

Bi-212,71-208 (0 36), Po 212 (0.64)

Ra-220 Po 216 I x 103 1 x 10' Rn-222 Po 218. Pb-214,51-214, Po 214 i

Ra-223 1 x 108 1 x 10

Rn-219 Po-215.Pb-211,Bi-211,71-207

)

Ra-224 Ra-220 Po 216 Pb 212 Bi 212,71-208 (0 36).P0 212 (0.64) i Ra-226 Rn-222. Po-218, Pb 214 Bi-214, Po 214, Pb 210. Bi-210, Po 210 i

1 x 101 1 x 10s Ra-228 Ac-228

%-226 Ra 222, Rn-218. Po 214 1*3M I*I h 228 Ra-224. Rn-220, Po-216, Pb 212 Bi-212,71-208 (0.36), Po 212 (0.64) 1 x 103 1 x 108 8

4 229 Ra-225. Ac-225,Pr-221, At-217.Bi-213,Po-213 Pb-209 1 x IOS 1 x 105

%.nat Ra-228, Ac-228, D-228, Ra-224, Rn-220, Po-216, Pb 212, Bi-212, 1 x 102 1 x 106' T1-208 (0.36), Po 212 (0.64)

! x 102 1xl@

1 x 102 1 x 108 U-230 Th-226, Ra-222, Rn 218. Po-214 U-232

%-228, Ra-224. Rn-220, Po-216. Pb 212 Bi-212,71-208 (0.36), Po-212 (0.64) 1 x 102 I x 107 U-235 Tb-231 g,j g,gp U-238 Th-234,Pa 234m U-nat

%-234. Pa-234m U-234, R230. Ra-226, Rn 222, Po-218. Pb-214, I x 1(,1 1 x 108 Bi-214,Po-214 Pb-210.Bi-210,Po-210 U.240 Np-240m I x 108 1 x 10' Np-237 Pa 233 1 x 102 1 x 106 Am-242n h 242 Am 243 Np239 1x19 1 x 108 (c)

The quantity may be determined from a measurement of the rate of decay or a 1 x 10 (b) 1 x 10 (b) measurement of the radiation level at a prescribed distance from the source.

1 7

(d)

Dese values apply only to compounds of uranium that take the chemical for 1 x 101 1 x 106 UO F and UO (NO )2 n both normal and accident conditions of transport.

i 22 3

3 Ix1@(b) 1 x 10 (b)

(e) 8 These values apply only to U

1-- 9 of uranium that take the chenucal form of UO,

UF,, UCI, and hexavalent compounds in both normal and accident conditions of 3

r nuclides with half-lives less N

(f)

These values apply to all compounds of uranium other than those specified in (d) an equilibrium are listed in the h-(g) These values apply to unirradiated uranium only.

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interim guidance for the safe transport of reprocessed uranium

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June 1994

4. APPLICATION OF THE REGULATIONS TO THE TRANSPORT OF REPROCESSED URANIUM 4.1. THE REGULATIONS

' SAGSTRAM has acknowledged that the current edition of the Regulations is unsatisfactory when applied to certain transports of reprocessed uranium. Having established l

a suitable dermition of unirradiated uranium, it is therefore necessary to derme how the Regulations should be applied to reprocessed uranium transport. This section provides a rationale for this, with expansions of the Regulations where appropriate to clarify uncertainties or inconsistencies.

4.2. APPIlCATION OF THE REGULATIONS 4.2.1. Principles of the Regulations The value of A for reprocessed uranium shall be determined using the composition of l

(a) 2 uranium isotopes and the amount of other radioactive impurities contained in the material, in accordance with the " formula for mixtures" stiputaled in paras 304 and 305 of the Regulations. Wherever the chemical form of a nuclide is known it is permissible to use the A value related to its known solubility class, taking the forms appropriate 2

to normal and accident conditions.

Reprocessed uranium whose specific activity does not exceed 10 A /g shall be classifie d

2 (b) as LSA-II. A may be taken as unlimited if 10 mg of the material contains less than the 2

ALI for that mixture, and such material can also thus be classified as LSA-II.

'f Reprocessed uranium not included in (b) above whose specific activity does not exce (c) 2 x 10-'A /g shall be classified as ISA-III if it can meet standards on teachability.

2 Uranium in a powder state may be classified as LSA-III provided it can be (d) demonstrated that there is no dispersal from a damaged package as dermed in para.

l 564(b)(i) of the Regulations.

The formula for determining the value of A is specified as follows in paras 304 and 2

305 of the Regulations:

1 1

-N A,for mixture = E' A (N l

2 l

Where f(i) : fraction of activity of nuclide i in the mixture, and A (i): appropriate A value for the nuclide i, e.g.

2 2

I SU: 3 x 108 Bq SU: 1 x 10' Bq

• U: no limit SU: 1 x 10'Bq mU: no limit l

l u

l For examples see Appendix VIII.

l 11 i

i 1