Text

UNC-2600 Container,Condensed Version for Certificate of Compliance
	ML19323C690
Person / Time
Site:	07105086
Issue date:	04/22/1980
From:	; UNITED NUCLEAR CORP., UNITED NUCLEAR CORP. (SUBS. OF UNC, INC.)
To:	;
Shared Package
ML19323C687	List: ML19323C686; ML19323C689; ML19323C690;
References
	16139, D-20354-6, NUDOCS 8005190013
	Download: ML19323C690 (1)
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CONSCLIDATED APPLICATION Page 2.

UNC 2600 SHIPPING CONTAINER USNRC CERTIFICATE OF COM*LIANCE 5086 1.2.2 Operational Features - Use of the package is simple and no discussion is provided.

1.2.3 Contents Of Package:

l (1) Type And Form Of Material:

(1)

Dry uranium-zirconium, uranium-aluminum alloys and compounds with densitias not exceeding 1 kg U235 per liter in the form of solids. Uranium may be enriched to any degree in the U235 isotope.

(1'i)

Dty uranium oxide pellets encapsulated in stain-less steel, aluminum or zircaloy rods. Uranium may be enriched to a maximum 5.0 w/o in the U235 i

isotope.

(iii) All materials are unirradiated.

(2) Maximum Quantity Of Material Per Package:

Ten (1) kilograms U235 and the net weight of the contents not to exceed 308 lbs.

(3) The cross section of the inner container shall be limited

)

to a maximum 19.6 square inches for the contents specified in 1.2.3 (1)(1) where the ratio of the weight of U235 to i

the weight of U235 plus zirconium exceeds 0.074 or the ratio of the weight of U235 to the weight of U235 plus alu=inum exceed 0.22.

2.

Structural Evaluation:

2.1 Structural Design:

2.1.1 Discussien - Paragraph 1.2.1(3) identified the principal constructional details. Rubber bumpers are used at either end to distribute any impacts from the cage assembly to the ends of the container. Due to the simplicity of the design, the =inimum loads to be carried, the 30 ft. drop testing /40" penetratien test acceptability testing, and long-time accept-l able ese, detailed design evaluation is not being made.

2.2

'4 eights And Center of Gravity:

The C.G. is essentially the center of the package and applies to loaded or unloaded condition.

2.3 Mechari:a1 ?rreerties of Materials:

l l

[

Structural caterial is sild steel for which a minimum yield point of 25.000 ;st and eini=um tensile of 50,000 psi wculd be typical.

I I

6 CONSOLIDATED APPLICATION Page 3.

UNC 2600 SHIPPING CONTAINER USNRC CERTIFICATE OF COMPLIANCE 5086 2.4 General Standards For All Packages:

2.4.1 Chemical And Galvanic Reactions - No reactions of concern would occur during shipment or accident conditions for reasonable exposures.

2.4.2 Positive Closure - The inner container is held closed by steel banding and the geometry restrictions of the retainer slot in the cage assembly of the outer container. Retainer plates are bolted to the cage assembly to hold both ends of the inner container in the cage.

The outer container lid is held closed by a lid ring which is bolted closed,with s tamper proof seal inserted in the end of the bolt 2.4.3 Lifting Devices - Only minor lifting is performed with hand trucks to place on hand truck or dolly to roll on or off transportation vehicle.

2.4.4 Tiedown Devices - Practice is as per 49 CFR 177.842(d).

2.5 Standards For Type B And Large Ouantity Packaging:

Not applicable.

2.6 Normal Conditions Of Transport:

2.6.1 Heat and 2.6.2 Cold:

No problems would be expected due to exposures to temperatures between -40 and +1300F, The rubber bumper would harden at the low temperature but still perform the distribution of stresses from movement of the cage assembly. Due to improvements in the quality of mild steel and the lack of appreciable stresses, no brittle fracture conditions would occur.

2.6.3 Pressure - Gradually, application would result in leakage through the lid seal and pressure equalization. Sudden appli-cation would result in dimpling of the walls of the outer container. There would be no loss in the geometry control or inner container retention of material.

2.6.4 Vibration - No effect.

2.6.5 Water Spray - No basic effect. Criticality control considers full moderation fron in-leakage.

2.6.6 Free Drop, 2.6.7 Cerner Drop, and 2.6.8 Penetration:

See later results of 20 ft. drop test and 40" penetration test.

e CONSOLIDATED APPLICATION Page 4.

UNC 2600 SHIPPING CONTAINER USNRC CERTIFICATE OF COMPLIA';CE 5086 2.6.9 Comoression - The application of a 6,000 lb. load uniformly to the " top" and " bottom" of the horizontal cylinder would not result in any compression as the nine (9) 3/8" steel plates distributed in the cage assembly would easily support this load.

2.7 Hvpothetical Accident Conditions 2.7.1 Free Drop and 2.7.2 Puncture Test:

b.

prototvoe testing:

(1) Date of Test or Evaluation - October 27, 1966.

(2) Location - UNC Fuels Division - New Haven Facility -

New Haven, Connecticut.

(3) k* eights - Drum (Tare) 804 lbs.

Load (Net) 308 lbs.

Total (Gross) 1,112 lbs.

(4) Description of Test or Evaluation - The ability of the I

subject container to withstand the hypothetical acciden*

conditions as specified by Title 10 CFR 71, effective August 22, 1966 has been evaluated by performing actual tests. The sealed inner container was loaded with a solid Inconel bar to simulate the weight of the SNM bearing material for which this container would be used.

The inner container was then inserted into the inner i

container support (birdcage) and the inner container and its supports were inserted into the outer container.

The outer container was then sealed in the same manner as planned for shipment. The outer container then was i

dropped from 30 ft. onto a concrete driveway in such a manner as to cause maximum deformation. The container initially hit on the edge of the lid with the remainder of the container continuing in a downward direction causing top, bottom, and side deformation. Following the free fall test, the container was dropped 40" onto a 6" diameter spike in such a manner as to cause =aximum damage to the container. Thermal and water immersion tests were not performed. The attached figures show several aspects of these tests (previously submitted in our January 3, 1967 submittal).

o 1

CONSOLIDATED APPLICATION Page 5.

UNC 2600 SHIPPING CONTAINER USNRC CERTIFICATE OF COMDLIANCE 5086 Figure No.

Description 1.

Container and internal supports prior to assembly.

2.

Container, inner supports and inner container during assembly.

3.

Container at free fall test position.

4.

Container showing damage after free fall test.

5.

Container with lid removed showing maximum damage after free fall test.

6.

Container and lid showing maximum damage af ter free fall test.

7.

Container during puncture test.

8.

Container showing maximum damage after puncture test.

9.

Inner container during disassembly after free fall and puncture tests showing negligible damage.

2.7.3 Thermal Test and 2.7.4 Water Immersion:

These tests were not performed since only materials that will not thermally decompose are shipped in these containers. The charing of the wood spacers and rubber bumper after 30 minutes at 1475 F would not affect the integrity of the package.

Th< nuclear safety of the individual centainers and array has beea evaluated with the assumption of inleakage of water.

2.7.5 Summarv Of Damage - The extent of damage after the 30 ft. free fall test is best shown en Figure 6.

This test caused a total deformation of approximately one inch at both ends and less than one inch along the length of the diameter. Damage caused by the puncture test is best shown on Figure 8.

The deforma-tion to the outer container was approximately 1/2" and there was no evidence of tearing or puncture af ter this test. Total damage to the container after these tests is shown on Figure 9.

Conclusions - The container was subjected to the test conditions I

specified by Title 10 CFR 71 with no resultant loss of contents and only minor deformation evident. The nuclear safety evalu-ation of this container has been performed assuming the above-noted amounts of deformation.

y

e a

CONSOLIDATED APPLICATION Page 6.

UNC 2600 SHIPPING CONTAINER USNRC CERTIFICATE OF COMPLIANCE 5086 2.8 Soecial For=:

Although most all the materials and items that would be shipped in the package would meet the requirements of special form, there is not a shipping advantage to be obtained since U235 has such a low relative radioactivity.

2.9 Fuel Rods:

While contributing containment due to cladding is present in many cases, the prime attribute is the material is in solid form, having no dimension less than 0.5 mm, and at least one dimension greater than 5 mm.

2.10 Appendix:

Pictures referred to in Paragraph 2.7.1 above should be placed in this Appendix.

3.

Thermal Evaluation:

Not required, as materials are not irradiated.

4 Containment :

4.1 Containment Boundarv:

4 While partial containment is associated with the outer container and inner container, primary retention is associated with the material being a solid phase, generally clad, with no piece having a dimension less than 0.5 mm and at least one dimension greater than 5 mm.

4.2 Reauirements For Normal Conditions Of Transport:

As indicated in Paragraph 2.6, the outer and inner container would withstand the test conditions of Appendix A to 10 CFR Part 71.

4.2.1 Release of Radioactive Material - As indicated in Paragraph 4.1 and 2.9 above, the form of the material to be transported, in addition to the integrity of the package would prevent the direct release of radioactive material fron the containment vessel.

a.2.2

?ressuri:ation of Containment Vessel 4.2.3 Coolant Containment

Not Applicable

/

i 4.2 a Caolant Loss

,j 4.3 Cert tinment Recuirements For The Hynethetital Aceident Conditions:

??.-

rpe testin; to requirements of Appendix 3 cf 10 CFR 71 was indi:stad i: Paragraph 2.7 above.

e e

CONSOLIDATED APPLICATION Page 7.

UNC 2600 SHIPPING CONTAINER USNRC CERT!FICATE CF COMPLIANCE 5086 4.3.1 Fission Gas Products - Not applicable.

4.3.2 Release of Contents - There would be no release of radio-active materials exceeding the maximum quantities defined in Paragraph 71.36(a)(2) of 10 CFR 71.

5.

Shielding Evaluation:

Not required due to low radioactivity of material to be transported.

6.

Criticality Evaluation:

Evaluation was made to the requirements of Table 6.1 of Regulatory Guide 7.9, Rev. I for Fissile Class II and III shipments (as per Para-graphs *1.39 and 71.40 of 10 CFR 71.

6A. Conditions:

A.

Each container will be limited to 10 kgs U235.

B.

The allowable number of containers will be suberitical unde normal and accident transport conditions.

C.

Under normal transport conditions, the array and its Ladividual con-tainers will be evaluated assuming:

1.

Individual Containers -

a.

Undamaged container b.

Container not internally moderated c.

Reflected 2.

Array -

a.

Undamaged containers b.

Cotitainers not internally moderated c.

Array reflected I

D.

Under accident transport conditions, the array end its individual containers will be evaluated assuming:

1.

Individual Containers -

1 Damaged container b.

Container internally moderated c.

Reflected 2.

Array -

a.

Damaged c:ntainers b.

Containers internally water moderated c.

Interspersed moderaticn between containers d.

Array reflected

o e

CONSOLIDATED APPLICATION Page 8.

UNC 2600 SHIPPING CONTAINER USNRC CERTIFICATE OF COMPLIANCE 5086 6A.

(Continued):

E.

The nuclear safe:y of the array under nor=al transport conditions will be evalua:ed using the density analog method. Accident transport conditions will be evaluated using the density analog and K

.ct-methods.

6B.

CAI CU'ATIONS A. ' Individual Containers' The s:ructural evaluatica tests shew dat individu:1 centainers should sustain ~

minimum da= age due to the impact results of an accident. Also, minimum damage shocid occur due to a subsequent fire since both the inner :nd outer contai:er are s:cel. The inleaksse of water :o.cause op:bu= v::sr coderativa within the container is assured for the accident condi iens. The inner container will h:ve a cross se'::ional area of 25 sq. inches or less.

Uraniu=- irconiu:2 elloys or ecmpounds. where the ratio of the weight of U-235 to the weight of U-235 ;1us zi : onium ex:ceds 0.074 vill he'pechaged in inner containers with cross-sections li=hed to 19.6 sq. inches or lars. The 25 sq. inch cross see: ion is safe fe; weight retics not en eding 0.074 a:

shown on the at: ached figure. The 19.6 sq. inch cro:: acc fou is ecyivalza:

to a 5 inch di:= cts: cylinder t+.Sh 'is safe for U-235 densitics not exc:edi,

1 kg U-235/11:or :: shown en rii;. 3, tin-7016, 2ev.1.

Uraniu=-:1u=inum alloys or co=peunds whers tN rzeic of the weish: of U-133 to the vaighc of U-235 pluc.4 -4 =:2 en:ced 0.22 vill b pachaged i= inner containce: vith c:::: sections lini ed to 19.6 :q. 6:hes or less. The 25 sq. inch cr:s4 :4c': Ten is enis for reish: r--^ - -- exceeding 0.22 :=

~

showa en the setached figuraM The 19.6 sq. inch b sie for U-235 densi:ler not exceed!.ns 1 kg U-135/litz: as sher.. abcve.

Using Tabla VIII, DP-1014, the sah d'-::: for 5". enriched ur niu.. cxids is Seft Diamets: = C~itical D'~-~{* c* a "U- ""

'"f --a t - x sisty F:c:3:

f23.4 + 20.

Ie 2

cm x.?3

=

= 8.2 in 2.45 c:./in

~

And the squivalent safe ::: s se:cicn,is 2

2 did g,,3*,

y Safe Cross Seccion =

=

= 52. S sq. inches 4

There for4, the 25 aq. heh ::ss: sa : ion O safe hr 5*. enrichsd uranks oxide us:arials.

s CONSOLIDATED APPLICATION Page 9.

UNC 2600 SHIPPING CONTAINER USNRC CERTIFICATE CF COMPLIANCE 5086 3.

Array of Containers

-~ '

"~

~

During transpercation, handling and storage, the. e containers could come into close proximity to each other. Therefore, the closest arrangement would be a triangular pitch. Under normal transport conditions, the undamaged container dimensions were used.

Se, d = 22.5", b = 101" The unit volume (V,) for the triangular pitch arrangement was obtained using V = 3.46 r b = 3.46 (11.25")2 x 101" = 724.46 u

The volume of the inner container is, V = cross sectional area x height = 25 in x 96" = 39.31 IC After the hypothetical accident and the resultant deformation, the container could come into closer proximity to each other again forming a triangular pitch.

Se, d= 22.5" - 0.5" = 22", b = 101" The unit volume under accident conditions was obtained using V,= 3.46 r b = 3.46 (11") x 101" = 693.42 8.

For the shipment under normal transport conditions, H/I < 2 is assumed.

From Table 1 and Fig. 8 of TID-7028, M,

= 48 kas U-235' [

=7.48kgsU-235//

b Actual Mass = 10 kg U-235 9, Actual Mass, 10 krs U-2357.48KgsU-235/.2,=1.342 s

p 3

f, Actual Nass, 10 hgs U-235 = 0.208 M

48 kga U-235 cb 5 = 2 (1-f) = 1.584 1 = 13 (from attached A ray Reflection Curve) u 1

724.46 g 1.584 I[Y 8

1 1 584 N, = pg \\ p

(

=

.206 x 13 1.34 /

s 0.37 (21000) = 7770 The allowable number of containers veuld be, Class II = 1554, Class ::: = 3885

a CONSOLIDATED APPLICATION Page 10.

UNC 2600 SHIPPING CONTAINER USNRC CERTIFICATE OF COMPLIANCE 5086 For H/X < 2 under accident conditions, from the attached interspersed Moderati~on Curve,

= 2.5 1

1 9

= 0.148(517.5)l.584 N.

e fR I V, /

.208 x 13 x 2.5 1.34 / /

g

= 0.148 (20000) = 2960 1ror E/X = 10 under accident conditions, from Table 1 and Fig. 8 of TID-7028 c,b= 25 kg U-235, f,b=2.27kgU-235/1 M

c

, Actual Mass,_10 kgs U-235

,4,4tg fcA 2.27 kgs U-235/4 a

1 Act'ual Mass 10 kgs U-235

= 0.4 H,.

25 kgs U-235 C o For a 25 sq. in. cross section, the equivalent diameter would be, __

1 4 x cross sectional area d=

f

= 5.64" (7.16 cm radius) with a 5.64" diameter (7.16 cm radius) and a V = 4.41

, the system height would be, s

4410 cc h =I r d(7.16 cm)

=

g s

h#

= 1*91

=

/d 14.32 cm Assuming a nominal reflector to describe the inner container wall, from Fig. 17, TID-7016, Rev. 1 Shape allowance factor = 1.2 Adjusting the actual mass to account for other than optimum h/d ratie, E W u lent Nass @.E} ~

" 0*

U U~

~

A ance Factor 2

b 8.33 kg U-235

,/'"M

., " 25 kg U-235

= 0.33*,

S = 2(1-d = 1.332 R x. I = 9.6 x 2.33 = 22.1 (from attached 4 ray aeflection Curve and Incarspersed Moderation Curve)

e CONSOLIDATED APPLICAIION Page 11.

UNC 2600 SHIPPING CONTAINER USNRC CERTIFICATE OF COMPLIANCE 5086 From Fig. F-1.1, Y-1272 fL g ".039 fl.g(each unit of 2 containers end-to-end) = I.I.fk. f= 0.49 steradians

= 0.245 steradians/ container l

The allowable number of containers would be "i

L'1ra'e'"1 container - S 87 + 2 cconcer unit) = 11.87 c.ntainers Under accident conditions for 3 layers, the outer container diameter, inner container diameter and edge-to-edge separation remain the same as for 2 layers.

Thus, also is the same A,3 x 101" 303"

= 53.7 5.64" 5.64" From Fig. F-1.1, Y-1272 ILg =.04

.OT(ea h unit of 3 containers end-to-end) = 4I.[1 = 0.5 steradians

= 0.167 steradians/ container The allowable number of containers would be 2.42 steradians A" 0.167 steradians/ container = 14.49 + 3 (center unit) = 17.49 containers Therefore, 17 containers as 3 layers subtends approximately the same solid angle as 11 containers 2 layers high. So the 2 layer case will be the limiting case.

For H/X = 30 under ccAdent condicions assuming 2 layers of containers Inner container Diameter = 5.64", Height = 2 x 101" = 202" Using K-1380, 7(f = 2.00 (Fig. I-5) 2 B

= 0.0619 + 0.0001 = 0.0620 (Fig. I-6) g,,

U = 0.322 (Fig. I-7) g B

= 0.1024 - 0.0001 = 0.1025 (Fig. I-8) g U.= 0. 987 (Fig. I-10)

K= 7(f U U.= 2.0 6 x 0. 322 x 0. 987 = 0. 655 g

CONSOLIDATED APPLICATION Page 12.

UNC 2600 SHIPPING CONTAINER USNRC CERTIFICATE OF COMPLIANCE 5085

[ V, h *

[693.42f 1.332 = 0.113(157.24)1.332 1

1 N=fg

,V,

=

c 4 x 22.1 4.41g 0;113 x 840 = 95 Since the density analog method is everly conservative for long cylinders, additional iteractens at higher H/X values will be performed using the k - A technique.

For R/X = 20 under accident conditions assuming 2 layers of containers, Inner Container Diameter = 5.64", Height = 2 z' Inner Container Height =

2 x 101" = 202" Using K-1380

% g= 2.07 (Fig. I-5)

B g,,g= 0.0619 + 0.0001 = 0.0620 (Fig.1-6)

U = 0.322 (Fig. I-7) g 2

B thermal = 0.1024 + 0.0001 = 0.1025 (Fig. I-8)

U = 0.987 (Fig. I-10) g k=%f U U = 2.07 x 0.322 x 0.987 = 0.658 g g The allowable A is determined using Allowable /l.= 9 -10 k = 2.42 steradians If 3 layers of containers are assumed, the height contribution to the Buckling i

values will decrease slightly. Therefore, both the thermal and fast utilization l

values should remain approximately the same for either 2 or 3 layers.

Under accident conditions for 2 layers, Outer Container Dia. = 22", Height = 101" Inner Container Dia. = 5.64" Assuming the units form a close packed array with a triangular pitch, there are up to six units surrounding the center unit and the edge to edge separation is, e - e = 22" - 5.64" = 16.36" A,2xh 2 x 101", 202"

,33,g d

5.64" 5.64" c=*;'=jjj"=2.9

=

CONSOLIDATED APPLICATION Page 13.

UNC 2600 SHIPPING CONTAINER USNRC CERTIFICATE OF COMPLIANCE 5086 The re fore, for H/X values greater than 20, k will decrease, the allowable.fL increase and the numier erf containers also will increase. Thus, 11 containers will be the limiting case. Assuming 11 containers to be the number critical, the allowable number af containers would be Class Il = 5, Class III - 10 the accident condities, will be the limiting case and determine the allowable number of contaf.ners.

References:

1.

TlD-7016, Rev. 1 - Nuclear Safety Guide, 1961.

Revised by: Subcon:=ittee 8 of the A=erican Standards Association Sectional Comnittee #6 and Project 8 of ANS Cor:nittee.

2.

DP-1014 - Critical & Safe Masses & Dimensions of U & UO2 Rods in Water (H. K. Clark, 2/66) 3.

TlD-7028 - Critical Dimensions of systems Containing U235, Pu239 & U233, 6/64 (Paxton, Thomas, Callihan, Johnson) 4.

K-1380

- Studies in Nuclear Safety (H. F. Henry, August, 1958) 5.

Y-1272, Y-12 Plant Nuclear Safety Handbook (Criticality Studies (T1D 4500 (20th Ed tion) ), 3/27/63 6.

NDEO-1050 - Criticality Safety calculation Method for Enriched Uranium -

Water Systems, UNC, Research & Engineering Center, Elmsford, New York by M. Raber, J. R. Tomento, August 22, 1967

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CONSOLIDATED APPLICATION Page 16.

UNC 2600 SHIPPING CONTAINER USNRC CERTIFICATE OF COMPLIANCE 5086 7.

Operatine Procedures:

7.1 Procedures For Loading The Package:

Procedures for packaging, labeling, inspection and release for shipping are given in our SNM Shipping Guide, Section 14.

An example of this procedure, together with associated route cards and inspection records, is in Appendix 7.4.

7.2 Procedures For Unloading The Packace:

Procedures for receiving and unloading are given in our SNM Shipping Guide, Section 13 (see example in Appendix 7.4).

7.3 Preparation Of An Emptv Packare For Transport:

See 7.1 above.

S.

Acceptance Tests And Maintenance Procram:

8.1 Acceptance Tests:

New packages would be subject to SNM Shipping Guide, Section 16 on Procurement or Modificatien of Shipping Containers (example given in Appendix 8.3) and our approved Q.A. program.

For these packages, only visual and dimension inspection would be perforned.

8.2 Maintenance I. ocram:

Our SN" Shipping Guide Section 14 in Appendix 7.3 covers this program.

.. ~

APPENDIX e.*

s SNM SHIPPING' GUIDE NUMBER:

O Section 14 SUBJECT UNC-NPD Packaging, labeling,' Inspection and Release for Shipping.

^

PURPOSE

]

To establish and define the requirements for packaging, labeling, inspection and releasing radioactive materials for transport.

APPLICABILITY All radioactive materials to be transported

!f the premises of the Naval Products Division to c,ther facilities either by UNC vehicles, common carriers or postal service.

Product shipment t r' customer (ERDA) is handled 'as required by contract.

RE S TRIC T '.'O N S l

1.

No radioactive materials are to be transported in UNC employee

privately owned vehicles.

2.

Only MBA Custodians or their delegates are authoriced to re-lease macerials for transfers.

RESPONSIBILITIES 1.

MBA Custodians or their delegates are responsible for directing the activities relating to packaging of radioactive materials as required in this procedure.

2.

The Plant Services Department is responsible for final over-checks and release of packages to carriers or UNC trucks.

3.

Health Physics (NIS) will perform required contamination and radiation survey.

P REP ARED BY : " '

w,e'Y

X a2 NUC*E M'

R' dS MAhAGER:

x.

mnp

'7//h/76 MANAGER:

L/'n/2 i

t PAGE 1 CF 3

NUMBER SNM SHIPPING GUIDE REV.

Section 14 v

4 PROCEDURE 1.

External Shipments To other Licensees a.

Verification verify that the recipient is authoriced to receive the type, form and quantity of SNM to be transferred (See Para. 70.42 of 10 CFR 70).

b.

Packacine at:d Inspection' (By NMC Personnel) 1.

For shipment in excess of exempt or small quantities of j

enriched U (see SNM Shipping Guide Section 2,3 and 4) only DCT specification or NRC/ DOT approved containers are to be used which have been authoriced by the NIS Department

~

via a " Container Specification and Inspection Report."

2.

Select the containers which are auth'oriced for the items and quantities to be packaged.

3.

Inspect, package, and document in accordance with Attachment A,

" Instructions for Completing Container Specification and Inspection Report (CSIR)".

Place tamper seals on containe'rs immediately after packaging and closing containers.

4.

Forward completed report to Nuclear Material Control (NMC) office, notify NIS of pending shipment, and request con-tamination and radiation survey of container.

c.

Survey and Release (By NMC Personnel) 1.

NMC obtain prior approval to make the shipment from the Consignee in accordance with his requirements, (e.g.,

SNM-KAPL requires a request by TWX and a TWX approval prior to releasing the shipment).

2.

NMC Foreman audit the CSIR to assure that the inspection is completed, quantities, and ite=s are in compliance with the authorication.

3.

Determine type of labels required, and other special controls required.

See SNM Shipping Guide, Sections E &

11.

4.

Initiate and prepare the followings a.

Radioactive labels (two for each container) and enter required data on the labela.

b.

Type A or Type B,

Fissile Radioactive or Radioactive Material.

c.

" Corrosive" label if necessary, d.

Factory Shipping Crder (FSO) - Reccrd required in-formation for internal centrel purposes, e.

Vehicle Placards.

e

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a..

r

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Por rd I c. 214 r.c M::C Pach.gsr for app'"ine to centr.ince Op?

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(.s cu.a. n t e listed in c.G wi11 arrange for the transfer cf coe -

tr.iner te the loading dcch cnd vill'arrsnge for e mo?c.

2.

T.:. c h cor.tainer will be final chacked by Shipping D pcrtrent.

{

f.: r li bcln, s:al numbe rs, -nicrkings, ote.ar shovn on the S5 :

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.P

SNM SHIPPING GUIDE NUMBER REV.

Section 14 0

5.

Small packages of small quantities of enriched U (See SNM Shipping Guide, Sections 2 & 4

) are authori=ed to be mailed.

(See U.S.

Postal Publicatior 46).

A label containing the following information is required on ;he outside of the package:

" Radioactive material, gamma radiation at surface of parcel less than,10 =illiroentgens for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

No significant alpha, beta, or neutron radiation".

The packages must meet the requirements of 2.a.1,2,

. and (a) the outside of the inner contaf er must bear the marking " Radioactive Material - No _abel Re-quired".

s Ob ). Liquid radioactive material must additiona17; be packaged within a leak and corrosion re-sistant inner container, surrounded by suf-ficient absorbent material to absorb at least twice the volume of liquid contents.

(a) Material classified as non-radioactive can be mailed. (See SNM Sh'ipping Guide, Section 1).

3.

Enpty containers Empty containers bearing radioactive markings or labels on the outside must be labeled with an " empty" label.

The label is six inches square with white background and letters in black at least one inch high.

The labels should bc weather-resistant and avoid peeling.

J I

i racz 3 er 3

~..

r m,=,.

-ATTACHMENT A SNM SHIPPING GUIDE NUMBER:

.EV. O i

INSTRUCTIOFS FOR COMPLETING " CONTAINER l

SPECIFICATION AND INSPECTION REPORT" (CSIR)

Section 14 i

A.

INTRODUCTION

This instruction is to be followed for all containers used to package radioactive materials (in excess of small quantities of enriched U ISee SNM Shipping Guide, Sections 2&43) which will be t,ransported off the premises of NPD, unless otherw'ise exempted.

Separate CSIR's for each shipping container are provided (attached:

Each form specifies the items to be inspected and the authorized contents B.

PACKAGING PROCEDU'RE (To be performed by " packager")

1.

Verify that the Specification Number and other markings required (as shown on the form) are plainly and durably marked.

For Standard Specification Containers this will be on the bottom of drum.

For DOT Cert. containers, thw 'ay be on a separate pla e welded to the container or may be painted on.

Record the serial number assigned to assign a number to identify,each container.

2.

Inspect the container to assure it is unimpaired, i.e.,

that

{-

there are no dents, tears, holes, cracks, etc., which may j

contribute to structural weakness or cause leakage.

Super-i ficial marks such as minor dents, chipped paint, scratches, etc., are not to be considered rejectable.

3.

Inspect all closure devices, gaskets, lids, bolt rings to insure that the integrity of these have been maintained.

l NOTE:

Any container whidh'is damated must be removed from h

use.

i I

PREFA.ED BY i

e b,7 v

l A N g /2 7g 4

c/,

NU"*E' MA*M 'ALS MANAGER:

-M

/

78

S 1

MANAGE 2:

2bd2 1 CF 2

....u.

~

SNM SHIPPING GUIDE NUMBER Attach. A REV.

Section 14 0

Containers requires repair:

Mark the container as "Under Repair - Do not use" by painting it directly on the drum or affixing a permanent type tag.

Issue a work order for the repair needed.

The means used to repair shall be recorded.

If tne container is damagsd such that it 1

cannot be re-used, then paint on the drum " Damaged - Not Re-Usable" and remove the container to a scrap disposal area for disposal.

4.

Prior to packaging any Radioactive Materials, verify that the items and quantition sre authorized for loading into the container.

5.

Package only those items as authorized on the CSIR.

NOTE:

A13 items which have exposed fuel must be wrapped, or placed in containers to prevent unnecessary contamination within the container.

Suitable cushioning and blocking of items should also be placed in the container to prevent inner packages or items from shifting during handling and transporting.

6.

Record the weights and items packaged as required on the form.

7.

Carefully inspect and affix all required closure devices to assure proper and secure closures.

Use and complete the step-by-step overcheck items shown on the CSIR.

8.

Record the gross weights on drums and check against allowable for container.

9.

All containers-must have a seal affixed to the container which is attached such that the seal would have to be broken to open the container.

Affixing the seal and recording of the number on the CSIR denotes that all overchecks have been completed and the container meets all the requirements listed and is, therefore, ready for shipment.

10. Sign and date the form when all has been comple,ted.

11.

Forward completed for=s to the designated office.

NOTE:

For all items which are inspected, enter your initials to denote it was acceptable.

If an item was rejected and repaired, enter "Rej-Rep."

File a written explanation of what was damaged and how repaired along with the CSIR.

PAGE :

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__y__

i TITLE:

NUMBER:

REV.

1 SNM SHIPPING GUIDE Section 13 SUBJECT Procedure for receiving radioactive shipments frem other licensees.

PURPOSE To establish and define area of responsibility for the ad=inistration of an e f f ective problem to assure full compliance w'ith regulatory require-ments for receiving shipments of radioactive material from other licensees PROCEDURT 1.

Upon receipt of containers of radioactive material or empty containers from other licensees, the Receiving Department shall inspect the con-tainer for. damage, signs of tampering, broken se12s, and' assure handling in accordance with any special instructions provided by shipper.

Ascertain that estimated and actual arrival times were in good Lgreement.

Check integrity of tamper seals within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of receipt time..

2.

A radia tion / contamination survey of each package and truck (where ap-plicable) received is to be performed by NIS w'ithin 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months of receipt of shipment if received duri.ng normal working hours or no later than 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months if, received after normal working hours..

NPD acceptance limits are:

300 DPM/100cm2 for removable surface con-tamination:

20 mR/hr at surface FROM INSIDE sources.

NRC and carrier must be immediately notified if above: 22,000 DPM/lOOcm2 for removable surface contamination; 2'00 mR/hr. at surface or 10 mR/hr at 3 ft. dis-tance from external surface of package.

3.

If any irregularities exist or damage is evident, set containers aside and notify NIS and/or Security Department (s) for special,in-structions.

PREPAPID BYi

< /* /

/

h/Yhl s l ft%,i,-),

i-nJ,.g/.,,Trif t.;S ::A:: AGER :

1:U CI,n tn

_ k' / *I h i,j, J '

HIS[ANAG2R:

/

e t

? AGE / OF 2 weem.

.m.

.w e

s n 1

~

NUMBER REV.

SNM SHIPPING GUIDE Section 13 0

a.

If any of the tamper-safing devices have been disturbed in a '

way that may indicate an attempt to render the device inoperable or if the device has been accidentally damaged, the following actions should be takens (1)

The affected containers should immediately be resealed I

with another tamper-safing device, and the resealing should be witnessed and attested to by the personnel delivering the, containers.

J (2)

The containers should be weighed and a determination made to whether any of the contents'have been removed.

as (3)

If the contents of the containers appear to be in order, the shipper should be notified and given the option of witn~essing.a quantitative assessm'ent of the containers' contents within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months following receipt of the shipment.

If the shipper does not respond to this offer, the contents of the container should be assessed as soon as possible but in no case later than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after receipt.

(4)

If the contents of the containers appear to have been re-moved, the shipper and the Director of the appropriate NRC Inspection and Enforcement Regional Office listed in Appendix A of 10 CFR Part 73 should be notified and given the' option of witnessing a quantitative assessment of the containers' contents within 24. hours following receipt.

If naither responds to this offer, the contehts of the con-tainer should be quantitatively assessed immediately and witnessed and attested to by personnel from at least two different groups within the receiver's organization.

4.

Accep table containers of radioactive materials received are to be transferred to '( and unpackaged by) the Nuclear Material Control Group.

5.

Prior to unpackaging, the NMC Grottp will check the' shipping papers accompanying the package for special instructions provided by the shipper for safe opening of the contain.er and handle accordingly.

6.

Prior to unpacking, the U-235 content shall be obtained from the shipper if act shown on packing list and handled in accordance with NOS authorization.

7.

Confirm weight of material received with shipping documents.

Fill out Form NRC-284 when NRC-741 cannot be completed within 10 days; report on NRC-741 within 30 days after receipt.

4 I

l PAGE CF 4

~.. >

h u.

7 __ _

PAGE:

3 PART IJLt!E Incoming S tif t SII I P M E rlT SERIAL /IDT !!Ut!B2R or Containing Shipment /Pkg. or IDPN-PACKAGES CONT. ON:

Empty Fuel Shipping Cont.

TIPICATIOtl REVISIOtt 110.

tiro CO!iTRACT on QUAT 1TITY tlOT E OPERATIO!!S 5 0,60 & 80 P.O.

ARE 110T P E RFO PflED POR EfLP_TY CO TIT _Al tl U R S

__________m OPER !!O.

OPERATIOli DESCRIPTIO!1 DR AW I t!GS, DOCUllEtITS OPERATOR

& llO R K REMARKS & STAMPS SIGt3ATURE/DATt titi i T 39yv7 010 Receipt Date Receipt Time By ACC REJ.

COttMENTS 9132 Receiving (Plant Services) Inspect Truck and Bill of Lading:

020 9132 A.

Proper Placarding D.

Shipment Firmly lleld On Truck U

b I

I C

C.

tio Visible Damage D.

Any Special llandling Instructions U

030 11 Survey / Smear External Surfaces of Containers, ACC.

REJ. COttt1ENTS

' ~ p*Cf frCoK 9132 A.

Removable Surface Contamination f1P D l

l l

l 2

Limits 300 DPit/100cm B.

Internal Radiation f1PD Limits 20mR/if at I

I external surfaces of pkg.

NRC f:aust be hoti fied immediately via NIS if in' excess of 22,000 DPH/lOOcm2 or'200 mR/l! at surface

,10 mR/It at 3 ft.

TPPROVALS:

NOTE: vur acc< mwo or eme. nevinove 8

/7& g!

f 7-2.qf",,,

on esma.ouitpr stavanetwis ce swtarts on

? L A::7 SERVICES:

9 WS 00C""t'if "'v at tunisuto as avatont A 'y [/jtr g> h,[A-f'

!1UC LE AR M ATE R1 M, CO!! TROL :

/

uMDt4 etDE AAL $1aTUIlS.

//

JUCLEAR & It3DUSTRI AL SAFI[IY I!? FORMATIO!I CATEGORY LNNh4.na)

Y{Y ad 2 h-76 TI!OhISED CLASSIFIER DATE i

r.o

. en PAhT tl1J1[; Incoming SNM

' S

th E t3T SERI AL/ LOT 21U!!HER oy I.

^,

I...IIT I F I CAT IO t!

PACKAGES Co n ta i rs i n Shipment /Pkg. or COrlT. Off

. r t ry t y I, u e Shapgng Cont.

I.. O Loth kACT OR QUAllTITY tIOT C OPERATIOtlS 50,60 & 89 RINISION ?!O.

i., o, 3 ARE NOT PERFORMED FOR F11P1Y C011T A EILR 9 l

')P E R. t:0.

DRAWING, DOCU!!EllTS OPERATOR OPERATION DESCRIPTICll y

REttARKS AND STAMPS SICt!ATURE/DATE/

I, g,ggy, l

li!!IT SilIFT

>a o Unload Vehicle. Check Each Container For ACC., REJ.

'J 412 A.

Taw. pet Proof Seal Intact. Verify.as soon as g

j g

g possible, but within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of receipt time of l

Oper.010 above.

YES tlONE O

l l

B.

Shipping Damage C.

Transfer to NMC Area IIMC Prepare to unpackage

YES, g

'r 050 A.

Check for Special Shipper Instructions for l

l l l

l 9722 Safe Opening B.

Obtain U235 content, type of material and l

l l

l other shipping information.

C.

Ilandle according to NIS authorization.

l l

YES NO NMC unpackage material.

Clean outside as necessary 000 and weigh.

Store in specified area, and handle in

[l

[

l 9722 accordance with NIS authorization. Confirm that ship-mnn'-

in enmp. lata a n ni n u a n t-i t-v in envenci--

NIS sample tor externdl cont 5minant on inside fuel ACC._

REJ.

070 package. Sample inside for empty containers.

[

l NPD Limits 300 DPM/ LOO cm2 9412 1

RECORD SPECIFIC PACKAGES SHEARED Ut!C complete required NRC-284 and/or IIRC-741.

080 9722 I

t **

gr*

APPENDIX 8.3 I

s PROCUREMENT OR MODIFICATION OF SHIPPING CONTAINERS (INCLUDING INNER Section 16 CONTAINER AND SUPPORTING STRUCTURE)

PURPOSE:

To define requirements for procurement of new shipping containers or modification of existing shipping containers.

LIMITATION:

This procedure does not' apply to shipping containers ordered by customers of UNC (i.e.,

contract item shipping containers).

REQUIREMENTS:

1.

Obtain NIS approval of any new modified container design.

NIS shall obtain any NRC/ DOT licensing approval required.

This requirement applies to standard DOT or special UNC containers.

2.

The purchase requisition / order shall include:

a.

Sufficient detail to completely describe the container.

b.

Test and inspection requirements.

c.

Certification requirement d.

Any field / receipt inspections by UNC and consequences of rejection.

Review DOT -49 CFR and 10 CFR 71 for some requirements.

3.

The purchase requisition shall include approval by NMC and NIS.

4.

Vendor certification / inspection data and any U0C field / receipt in-spection data shall be retained on file by NMC.

5.

Any requirement for field / receipt inspection (sample, partial or complete) shall be set forth by NMC personnel.

l PREPARID BY :.

gas NUCLEAR MATERIANS,MANACER-4(kWff&/_

I I

NIS MAN GER:

/

& %, n A r s mp d'hb PAGE 1 CF 1

--

ML19323C690

Text

References:

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