ML20126H875
| ML20126H875 | |
| Person / Time | |
|---|---|
| Site: | 07105059 |
| Issue date: | 03/27/1981 |
| From: | NUCLEAR FUEL SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20126H872 | List: |
| References | |
| 18819, NUDOCS 8104220203 | |
| Download: ML20126H875 (30) | |
Text
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[x CCNSOLICATED AFPLICATION FCR REfiEWAL OF CERTIFICATE CF COMPLIANCE FOR I'.Z EL fl0.
NFS URAiHL f41TRATE TA.% TRAILER Certificate fio. 5053 Fackage Identi ficalion i;o.
u3A/5059/AF i
Submitted By:
Nuclear Fuel Services, Inc.
P. O. Box 213 Erwin, TN 37650 1
'810422Oh03 193 2
TABLE OF CONTENTS Pace Rev.
Date 1.0 GENERAL INFORMATION 1-1 0
3/27/81 f
1.1 Introduction 1-1 0
3/27/81 1.2 Package Description 1-1 0
3/27/81 1.2.1 Packaging 1-1 0
3/27/81 1.2.2 Operational Features 1-1 0
3/27/81 1.2.3 Contents of Packaging 1-1 0
3/27/81 1.3 Appendix A Appendix B Appendix C 2.0 STRUCTURAL EVALUATION 2-1 0
3/27/81 2.1 Structural Design 2-1 0
3/27/81 2.1.1 Discussion 2-1 0
3/27/81 2.1.2 Design Criteria 2-1 0
3/27/81 2.2 Weights and Centers of Gravity 2-1 0
3/27/81 2.3 Mechanical Prcperties of Materials 2-1 0
3/27/81 2.4 General Standards for All Packages 2-1 0
3/27/31 2.4.1 Chemical and Galvanic Reactions 2-1 0
3/27/81 2.4.2 Positive Closure 2-1 0
3/27/81 2.4.3 Lifting Devices 2-2 0
3/27/81 2.4.4 Tiedown Devices 2-2 0
3/27/81 2.5 Standards for Packaging 2-2 0
3/27/81 2.6 Normal Conditions of Transport 2-2 0
3/27/81 2.6.1 Heat 2-2 0
3/27/81 2.6.2 Cold 2-2 0
3/27/81 2.6.3 Other Conditions 2-3 0
3/27/81 2.7 Hypothetical Accident Conditions 2-4 0
3/27/81 2.7.1 Thermal 2-4 0
3/27/81 2.7.2 Other Conditions 2-5 0
3/27/81 2.8 Special Form 2-5 0
3/27/81 2.9 Appendix A Appendix B
/
3.0 THERMAL EVALUATION 3-1 0
3/27/81
TABLE OF CONTENTS (Cont'd. )
j Page Rev.
Date 4.0 CONTAINMENT 4-1 0
3/27/81 4.1 Containment Boundary 4-1 0
3/27/81 4.1.1 Containment Vessel 4-1 0
3/27/81 i
4.1.2 Containment Penetrations 4-1 0
3/27/31 4.1.3 Seals and Welds 4-1 0
3/27/81 4.1.4 Closure 4-2 0
3/27/81 4.2 Requirements for Normal Conditions 4-2 0
3/27/81 of Transport 4.3 Requirements for Hypothetical 4-2 0
3/27/31 Conditions of Transport 4.4 Appendix A Appendix B 5.0 SHIELDING EVALUATION 5-1 0
3/27/81
6.0 CRITICALITY EVALUATION
6-1 0
3/27/81 6.1 Discussion and Results 6-1 0
3/27/81 7.0 CPERATING PROCEDURES 7-1 0
3/27/81 7.1 Procedures for Lcading the Package 7-1 0
3/27/81 7.2 Procedures for Unloading the Package 7-1 0
3/27/81 7.3 Preparation of an Empty Package for 7-1 0
3/27/81 Transport 8.0 ACCEPTANCE TEST AND MAINTENANCE PROGRAM 8-1 0
3/27/81 I
8.1 Acceptance Tests 8-1 0
3/27/81 8.1.1 Visual Inspection 8-1 0
3/27/81 8.1.2 Structural and Pressure Tests 8-1 0
3/27/81 8.1.3 Leak Tests 8-1 0
3/27/81 8.1.4 Component Tests 8-1 0
3/27/81 8.1.4.1 Rupture Discs 8-1 0
3/27/81 8.1.4.2 Gaskets 8-1 0
3/27/81 8.2 Maintenance Program 8-1 0
3/27/81 8.2.1 Structural and Pressure Tests 8-1 0
3/27/81 8.2.2 Leak Tests 8-2 0
3/27/81 8.2.3 Subsystem Maintenance 8-2 0
3/27/81 8.2.4 Rupture Discs and Gaskets on 8-2 0
3/27/81 1
Containment Vessel a
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Rev. O March 27, 1981 1.0 GENERAL 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 N ^ trate Hexa-hydrate Solution.
The package is shipped Fissile Class 111 and only one package is permitted per shipment.
The applicable portions of the format described in Regulatory Guide 7.9
" Standard Format and Content of Part 71 Applications for Approval of Packaging of Type B, large Quantity, and Fissile Radioactive Material",
will be followed in this application.
1.2 Packane Description 1.2.1 Packsaing The weight of the tank trailer is 14,000 counds and it will carry up to 45,600 pounds of sciation.
The tank trailer is constructed in accorcance witn 00T specifications MC-310, MC-211, or MC-312.
The 3,600 gallon insulatad tant, is of all welded construction.
The tank which is the containment vessel is 3/15 inch type 304 L stainles s steel.
All welds are 100%
X-r ay ed.
Tne tana has no cottua outiets.
The Ic5Ginc port is loc;tEd en tha tap rear cf tha ::nk, ;nd
,0 other at: ass to tha tank is p;ovided.
The tank is designed f:r cperation at 35 PSIG.
Tne rermal pressure in trs, sit,ill be essentially at:cs-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 Packaoing 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 Ni'trate is the final product of a facility which recovars unirrdiated low enriched uranium, no other isotopes are present in significant quantities.
The total uranium content shall not. exceed 357 grams per liter.
The nitric acid concentration will normally be 1.CM or less.
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2.0- STRUCTURAL EVALUATION j
2.1 Structural Desicn 2.1.1 Discussion The tank trailer meets or exceeds the requirement of DOT speci-fication MC-312.
Modifications described in 1.2.1 were made in an effort to prevent and control leakage from the tank.
2.1.2 Desian Criteria
)
The tank meets or exceeds the design criteria for DOE speci-1 fication MC-312 (49 CFR 178.3a3), cargo tanks.
The presence of low enriched uranium does not add any physical or chemical properties to tne solution that woulo require upgrading of these design criteria.
2.2 Weights and Centers of Gravitv i
Because of the cylindrical shape of the tank, the center of gravity for both a full or empty tank will be the same as the gec.Tetric center of the tank.
The adcitional weight of the access port, spill tank and retainer pans do not significantly change the center or gravity.
Partial ioads, of co0r ce, have the ef fect of lostering the center of Gravity.
The weights of the tank trailer and contents are given in Section 1.2.1.
2.3 Mechanical Procerties of Material The tank is entirely constructed of type 304 L austenitic stainless steel.
In accordance with Specification MC-312, the steel thickness is more than adequate to handle the weight of the uranyl nitrate solution.
2.4 General Standards for all Packaoes 2.4.1 Chemical and Galvanic Reactions The 304 stainless steel is more than adecuste to withstand the corrosiveness of the nitric acid concentrations present in the Uranyl Nitrate solution.
No galvanic or other reactions occur between the tank and the contents.
2.4.2 Positive Closure The cover assembly is shown in Appendix 1.3.
The main cover is held in position by 16 locking bolts.
Three small inlets on the main cover, as well as the rupture disc are closed by flanges with 4 bolts to each flange.
The main cover is protected on top and all four sides by a stainless steel double walled insulated enclosure wnich is provided for padlocking.
2-2 Rev. O i
March 27, 1981 i
2.4.3 Lifting Devices L
No lifting devices are utilized.
l 2.4.4 Tiedown Devices No tiedown devices are utilized.
The tank is fixed to the i
trailer in accordance with specification MC312 requirements.
2.5 Standards for Packaainq l
Current DOT regulations authorize the shipments of radioactive liquids a
of specification MC-310, MC-311, MC-312 or MC-331 cargo tanks where the i
radioactivity concentration does not exceed 10% of Low Specific Activity 4
(LSA) levels ( 173.392).
The 00T regulations further exemnt these
+
4 j
cargo tanks from the general reouirem+nts for type A packaging 4
(173,393).
The contents aescribed in this acplication can not be shipped in accordance with the requirements because tney are classified i
as fissile material.
This application tnen will demonstrate that the fissile property of the material can be adequately dealt with both j
under normai and accicent conditions.
2.6' Normal Corditions of Transcort The effect that nornal conditions of tran port have on the nuclear j
criticality safety of the tank trailer will be examined in this section.
2.6.1 Heat i
Heatinc of the solution in the tanker could cause evaporation of the solution and result in increasing the fissile concentration.
Because the trailer is insulated, heat from normal transport has 4
little or no effect on the concentration.
The conclusion is made from the results of the calculations in Section 2.7 dealing with the effects of heat under hypothetical accident conditions.
l 2.6.2 Cold i
l The normal effect of cold weather poses the only threat to the criticality safety of the tanker.
These effects can be easily dealt with.
Under certain conditions of uranium concentration, j
acid concentration, and temperature, it is possible for the uranyl nitrate to crystalize and precipitate.
The of fectiveness of the tank insulation as a preventative measure against the solution freezing under cold weather condi-tions encountt ad in transport was evaluated.
The freezing point of the iA (NO )96H0watersolutioningheconcentration 3
g j
range of soluti0n to bg whipped varies from 0 C for very low ccncentrations to - 15 C at 20% UNH.
These values were taken from Figure 4.7, p. 117, Reactor Handbook, 2nd edition, Volume II, Stoller and Richards.
The freezing temperature is further depressed in this concentration range oy the presence of HNO3 4
4 i-
2-3
+
Rev. 0 March 27, 1981 1
up to 0.8M.
Above this acid concentration, the freezing point of the highest UNH solution concentration increases from -21 C and reaches 0"C at 2.00 HNO.
This is shown in Figure 4.8, p.
3 117 of the Reactor Hancbook No solution will be shipped that has a ccmbination of UNH, HNO g
3 and water resulting in a freezing point higher than 0 C.
The package which consists of stainless steel and glass wool suffersnofossofeffectivenesswhenexposedtotemperaturesas low as - 45 F, which is twice as severe as the lowest gempera-tures recorded in the Southeast.
A temperature of -22 F was selected as the minimum average day and night temperature that could occur over a four-day period.
In practice, solution will g
not be packaged for shipment when temoeratures are below 0 F.
A maximum certed of four days of severe weather exposure was selected on the e sis tMt two days is the ncrmai travel tir2 to the farthest destination known at present tnus allowing far censicerable delay enroute.
A thermo., ell is provided near the bottom of the tank so that the dr:ver can reasa... plution temperature daily if a delay occurs during cold wear e' The driver is given written instruc-tiens to lay cwer in a h.
ca caraae when the sciution te7 era-g tures cet c a n to 32 F.
ne is instru:t.ed to lay over until the solutien ter.:u:tura reaches 40F or until tha c;ytime outsic.e ter;2rature is 32"F or higher.
U Urder the a~ove conditions, with product loaded at 65 F into the c
tank which has a minimum of four inches of glass wool insulatic:
as specified, ghe decrease in solution temperature was deter-mined to be 10 F in four days.
This computation is shown in section 2.9, Appendix A.
The large safety factor provided by the insulation is to allow for safe shipment of less than full tanks of solution.
As little as 1,300 gallons (1/2 tank) of solution can be safely shipped under the severe weather condi-tions encountered.
It can be noted that solution ct, be safely transported at average temperatures as low as c2"F without fear of freezing when controlled as specified in this section.
2.6.3 O ther' Condi tions At worst, the other applicable normal conditions of transport could result in some leakage from the tanker.
Although this leakage would not result in a criticality, it would of course create a contamination problem.
The following precautions have been taken to minimize the possibility of such an occurance; a.
The tank wall has been increased in thickness from 10 gauge required by MC-312 specifications to 3/16 inch.
9
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a
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s 2-4 Rev. O March 27, 1931 b.
The tank and connections are of all welded construction, c.
All tank welds are to be 100";; X-rayed, d.
The tank has no bottom outlets.
e.
The tank is designed for operation at 35 psig, shereas, the pressure in transit will be essentially atmospheric.
f.
The tank is to be tested in accordance with MC-312 and ASME Specifications including a hydrostatic test at 55 psig.
g.
The tank will be retested as in (f) after each two years of se.vica instead of every five years as specified in the 00T P.egul a t i o ns,
h.
All tank outlets will be securely closed with teflon gas-kets and blind flanges while in transit.
i.
In the event the tank were to develop a leak, it would probably start as a small leak through a weld.
Water-tight retainer pans have been provided underneath the full length of the tank to ccliect such leakage.
There is a capped, drainage and inspection nozzle in the bottom of each pan.
These are to be removed and inspected tor leakage after each use of the tank.
If solution is found, incicating a leak in the tank, the tank trailer will not be reund until it has been repaired and successfully tested as in (f) above.
2.7 Hypothetical Accident Conditions The only hypothetical accident condition that could possibly result in criticality is heating and evaporation of the solution, thus increasing its uranium concentration.
This is examined in this section.
2.7.1 Thermal Theeffectofanaccjdentinwhichtheentire38feetoftank were exposed to 1475 F for 30 minutes was evaluated.
In making this evaluation, it was assumed for consergatism that the ex-ternal stainless steel wrapper was at 1475 F for the entire period and that heat flow was by conduction.
The increase in solution temperature was found to be an insignificant 1"F.
This computation is found in cection 2.9 Appendix B.
Since the iowgst boiling temperature of any solution to be shipped is 212 F, it can be stated that an increase in the U-235 concen-tration by evaporation to the concentration required for a fission reaction to occur under any conditions encountered in transport is not credible.
It is recognized that the stainless steel exterior wrapper would probably suf fer some distortion from exposure to the 1475'F fire and that the outer surface of the glass woni insulation would lose its effectiveness as insula-tion during the course of the fire.
The glass reacnes the g
sof tening point at about 1200 F.
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2-5 Rev. 0 March 27,-1981 2.7.2 Other Conditions 1
The other applicable accident conditions were examined to deter-mine if.any could result in criticality.
This examination resulted in all cases to show that the possibility of criti-cality is' reduced since the fissile concentration rather than
)
increasing remains tne same or decreases.
2.8 Special Form i
.The special torm classification is not claimed for the contents of the tank trailer.
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Rev. O March 27,1981.
2.9 Apcoraix A Determinatica of insulation effectiveness in the prevention of solution crystallization at icw temperature in air.
Data:
Tank diameter D = 4 feet Time exposed 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> Average outside temperatuer t = -22 F g
Solution temperature initial t) = 69 F g
Heat transt,
cate cf insulation k = 0.024 (CTU)/(hr.)(ft.')(CF)/ft.
Insulation thickness L = 0.33 ft.
Surf ace un for 1 ft. section = A = D = 12.5 ft.2 Solution weight (W) at to. gr. of 1 = 7SO lbs.
Solution so. ht. (C,) = 1 (Reascnably acdurate so icn; as sp. gr. assumea to be that of water for tne various concentrat. ions )
Computations:
^
Heat transferred = q = M a t q = 0.024 x 12.5a t O.33
=0.91 a t a t = t) -to
= 68 - (-22) = 90 F This assumption is conservative since t) will decrease Total q = 0.91 x 90 x 96 = 7,850 BTU q=WCa19 p
at. = 10 F i
Final solution temperature = 68 - 10 = 58 F Solution freezing point = 32 F
- _ ~ _ _ _
Rev. O March 27, 1931 i
2.9 Appendix B tank exposed to 1,475,erature increase in' uranyl nitrate solution in Determination of temp F radiant heat for 30 minutes.
Data:
Tank diameter D = 4 feet Specific heat of solution C
=1 (Reasonably accurate f8r the concentrations of interest when specific gravity is assumed not to change.)
Insulation thickness L = 0.33 feet l
Thermal ' conductivity of insulation = 0.024 BIU/(hr. )
(ft.')("F)/ft.
0 Solution temperature, initial tj = 100 F 1,475 F Outside te.~perature t
=
g Surface heated A =- D x 1 = 12.5 ft.2 (Since cylinder is long - about 38 feet - end effects are ignored and aralysis is made of I foot wide section.)
Solution weight W at sp. gr. of water =
r2 x 62.4 = 730 lbs.
Comput: tion:
Heat transferred q (assuming conductivity is controlling)
= kA a t
~
L
= 0.024 x 12.5 a t 0.33
= 0.91 at BTU /hr.
At=t
-t o
g
= 1,475 - 100 = 1,375 F Assumes no increase in T $
Total q = 0.5 x 0.91 x 1,375
= 625 BTU during the period of the test at
=
a S
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Rev.'O March 27, 1931
[
l r
= 625 0F=1F t
780 x 1 Final solution temperatures = 100 + 1
= 101 F Solution boiling temperature = 212 F i
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3-1 Rev. O March 27, 1981 l
3.0 THERPAL EVALUATION Because of the possible effects that cold from normal transport condi-tions and heat frem accident conditions have on the nuclear criticality safety of the contents of the pactage, four inches of insulation is provided for the tank.
This protection minimi;es these ef fects.
Because no internal heat is generated frcm the contents, the tanker trailer does not utilize any cooling systems, expansion tanks, etc.
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41 Rev. O March 27, 1931 4.0 CONTAINMENT This chapter identifies and discusses the package containment.
4.1 Containment Boundary The containment boundary claimed for the package is the tank shown in Section 1.3 Appendix A.
4.1.1 Containment Vessel The containment tank is constructed of Type 304L stainless steel.
No heat treatment is required.
Head and tank wall thickness is 3/16 inch.
Materials of construction shall ccmply with NFS Materials of Construction Standard Engineering Speci-fications (Section 4.4, Appendix A).
The tank is of all welded constructicn end contains no baffles.
4.1.2 Containment Penetrations A 20" diameter manhole is the main Denetration in the crtain-ment tank.
The manhole is located at the rear top of tne tank and contains four flanges as follows:
a.
3" filling flange b.
3" unloading flange with remaveable 2" dip tube.
c.
A standard 40 poend rupture disk outlet, d.
I 1/2" flange nozzle for air supply and relief.
All nozzles are furnished with envelope type teflon gaskets and type 304 stainless steel blind flanges.
The manhole cover is secured by swing bolts and wing nuts through which a chain may be run and padlocked to prevent un-authorized access to the tark or connections.
The manhole is protected by an insulated stainless steel spill box.
Any leakage into the spill box drains into the spill tank as shown in Strtica 1.3, Appendix C.
4.1.3 Seals and Welds All seals are made with envelope type teflon gaskets and type 304 stainiass steel blind flanges.
Tank welds are 100% X-rayed, and the tank is hydrostatically tested for leaks in accordance with the ASME Specification, as required by NF5 Process Equipment Standards Engineering Speci-fication; Fabrication Requirements for Authentic Stainless Steel Tanks.
(Section 4.4, Appendix B).
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4.g Rev. O March 27, 1981 4.1.4 Closure The closure devices fcr tr.e tank are the manhole cover flanges described in Section 4.1.2.
4.2 Reauire. Tents for Normal Conditions of Transport The tank trailer is exempt frcm these requirements.
4.3 Recuirements for Hycothetical Accident Conditions The tank trailer is exempt f rom these requirements.
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l 4.4 APDendix A Nuclear Fuel Services, Inc.
Materials of Construction.
Standard Engineering Specification 1.
SCOPE 1.1 This Specification covers wrought austenitic stainless steel for use in corrosive services where intergranular corrosion can occur.
1 1.2 Where clad materials are involved, it is the intent of this i
Specification that the alloy-clad material shall meet the requirements for this grade as specified.
2.
COMPOSITION 2.1 The chemical composition of the alloy covered in this Specification shall conform to the following analyses:
Type:
304L austenitic stainless steel Chcmical Composition (Percent)
Carb;n (max.)
0.03 Chrcaiam (min.)
18.0 Nickel (min.)
8.0 Mangerese (max.)
2.00 Silicon (max.)
1.00 Sulfur (max.)
0.03 Phosphorus (max.)
0.04 2.2 Chemical analyses of all material purchased shall be supplied.
NQt Required 3.
HEAT TREATMENT 4.
SURFACE FINISH 4.1 All material shall be cleaned of its heat-treatment scale or other foreign surface contamination by sandblasting, salt bath cleaning followed by pickling, or by pickling alone.
It is important that the pickling be the final step in cleaning and that the pickling acid be thoroughly washed from the surface of the steel with clean water.
Any of the commercially used pickling solutions (except hydrocnloric acid or other chlerides) capable of dissolving free iron or iron oxide may be used.
The surface shall not be pitted or i
intergranularly attacked to a degree tnat would be con-sidered harmful.
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1 Rev. O March 27, 1981 5.
TOLERANCES 5.1 Plate, sheet, strip,'and bar furnished to this Specifi-cation shall meet the requirements for variations in aimen-i sions and workmanship listed in the Steel Products Manual, i
Section 24 (published by American Iron and Steel Insti-I tutes, 350 Fifth Avenue, Nes York 1, New York).
6.
INSPECTION 6.1 Inspection, unless specifically waived, shall be made by a NFS representative prior to shipment.
Notice shall be given at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> in advance of the availability of l
material in order to provide for inspection scheduling and prompt release.
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. s Rev. O March 27, 1931 4.4 Acoendix 3 Nuclear Fuei Services, Inc.
Process Equipment Standard Engineering Specificaticn Fabrication Pequirements for Austenitic Stainless Steel Tanks 1.
SCOPE 1.1 This Specification covers fabrication and inspection of aquipment built of the 300 Series austenitic stainless steel.
It is a supplement to the drawings and other speci-fication: incluced in the order.
2.
FABRICATOR'S DRAWINGS 2.1 Fabricator shall submit drawings as specified on other attachments made a part of the order.
2.2 Drawings submitted'must be in sufficient detail to show clearly materials of constructico, typical v. eld details, dimensions, tolerances, NFS order nurcer and gasket speci-fications, weight amaty and weight full of water, and other information necessary f or checking against all specifi-cations prior to apprcval.
In accition, crawings of pres-sure vessels will shcw the design temperature, design pressure, ana tne test pressure.
2.3 NFS approval of f abricator's drawings does not relieve the fabricator of the responsibility for Code compliance and the intent of this Specification.
3.
MATERIALS I
3.1 Material by the Fabricator.
When the material is supplied by the f abricator, he will accept and carry cut the require-ments of paragraphs 3.1.1 and 3.1.2 inclusive.
3.1.1 Two copies of all orders for stainless steel mate-rial, identified with NFS order number shall be sent to Nuclear Fuel Services, Inc., Box 124, West Valley, New York.
3.1.2 Commercial Grade stainless steel.
Inspection of this material by NFS at the mill is not required, and corrosion coupons are not required; however, material must be properly identified and mill test reports showing chemical analysis are to be supplied. When ASME Code requirments must be met, j
the mill test reports must also show mechanical properties, j
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Rev. O March 27, 1981 4.
FABRICATION 4.1 All stainless steel is to be identified throughout fabri-cation.
The identity of "Com.rercial" stainless steel according to type number is to be maintained throughout fabrication.
4.2 If oxyacetylene powder cutting, metallic electrode arc cutting, or " Arc-Air" is used, the joint edges shall be ground to remove gouges and produce a clean, bright sur-face.
If carbon arc cutting is used, at least 1/16 inch of metal must be subsequently removed from the cut edge by machining or grinding.
4.3 Carbon stoel clamps, supports, braces, etc. shall not be welded directly to any interior surf aces of stainless steel units nor directly to tne exterior of units wnich are under 1/4 inch in thickness.
4.4 Distortion.
Machined surfaces, such as body and.anhole flanges, which are warped or otherwise distortec cue to the subsequent welding, heat-treatment, or assembly, are to be remachined after tnese operations have been ca.mpleted.
4.5 Material thicknesses, after final machinir.g, shall ce as specifiac on the dra.iing, ths oraer, or other s;e:ifi-cations fer those parts.
4.6 Full X-ray of all welded lengitudinal or.d circumferential joints is required on the tank and tank nc::les.
4.7 Fine grained film shall be employed for X-ray examinations.
4.8 Tolerances.
All equipment shall meet the manufacturing tolerances shown on the order or the drawings.
The out-of-roundness of all shells or containers shall meet the requirements of the ASME Code for Untired Pressure Vessels for internal or external pressure, whichever is applicable.
4.9 Machined surfaces must be finished to the smoothness limit specified on the drawing.
5.
WELDING 5.1 Only the inert gas shielded-arc, metallic-arc-coated elec-trode, or submerged-arc welding processes are to be used.
The fabricator is to state in his quotation the type of welding which will be used.
5.2 Welding grade argon (99.99 percent purity) or helium (99.99 percent purity) or dry nitrogen (0.3 percent maximum oxy-gen, minus 60 degrees C dew point) may be used to back up inert gas shielded-arc welds.
The gas backup technique shall provide a bright, or only slightly tarnished surface on the underside of the joints.
Rev. O March 27, 1931 5.3 The welding processes and operators must be qualified prior to fabrication in accordance with Section IX of the ASME Code.
5.4 Full per,etration'is to be obtained in all butt welds, and in other joints as specified, by back chipping or other means.
5.5 Eack chipping, grinding, or gouging is required to cbtain full penetration in all double-welded butt seams or other full penetration joints.
Back chipping is to be performed with a round-nosed tool having a minimum radius of 1/8 inch and is to be continued until sound metal is reached.
In no case is a V-shaped. tool to be used, as this results in a V groove which is difficult to weld without slag inclusions and lack of penetration in the root.
When other methods such as grinaing are employed, the resulting gecove must have a radius of at least 1/3 inch.
5.6 The welding filler metal (sire or electrede) shall conform to ASTM a 253 or a 371 specifications and shall deposit metal comcarable in ch:mical ccmposition :nd echanical properties to those at tne parenc natal.
Tna r;aricator is to maintain a system to assure trat only the proper welding wire and electrodes are used in the fabri:ation, 5.7 Welds between stainless steel and carben stael cre to be made with ER-310 (25-2C) electroGes.
Welding procadures for joining materials of dif ferent analysis (dissinilar metals) shall be qualified in accoraance witn the ASME Code.
5.8 All welds exposed to the inside of the tank shall be made from the inside and shall conform to vendor semple weld.
6.
CLEANING 6.1 All egr pment fabricated according to this Specification is to be free of weld flux, spatter, arc-burns, gouges, tool marks, oil, grease, and general shop soil.
7.
INSPECTION 7.1 All equipment fabricated in accordance with this Speci-fication is subject to NFS inspection.
The NFS Inspector shall be permitted free access at all times to such loca-tions as are concerned with the supply or manufacture of the materials or equipment involved.
The manufacturer shall furnish such equipment, assistance, and facilities for inspecting, checking, and testing as may be necessary for safely carrying out the complete inspection require-ments.
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Rev. O 2
March 27,1981 7.2 Final Inspection.
Af ter fabrication is complete, a final inspection shall be made which will include examining radiographs and witnessing hydrostatic and other specified tests.
For checking "as built" dimensions, alignment of vessel parts, tilt and orientation of no::els, etc., the equipment shall be leveled and reference points estab-lished.
8.
TESTIllG 8.1 The NFS inspector shall be given the opportunity to witness all pressure tests, running tests, or other special tests as required by the ICC or ASME Codes, drawings, order, or specifications.
8.2 All welds are to be sufficiently cleared prior to hydro-static testing to permit procer examinstion for cefects.
8.3 The final hydrostatic test pressure shall be held for a minimum of one hour.
For equipment requiring a " water-tightness" test, such as drip pans, the units shall be allowed to stand full of water a minimum of four hours.
8.4 Gaskets specified on the order or drawings shall be supplied by the f abricator unless specifically noted other-wise.
Gaskets used for test purpose must ha.a the same dimension; anri compressibility as the service gaskets.
Gasket compounds, pipe cope, or other sealine materials shall not be used under any conditions.
9.
PAINTING 9.1 All non-stainless steel structures shall be properly primed and finished with aluminum paint.
4 5-1 Rev. 0 liarch 27, 1981 i -
5.0 SHICLDING EVALUATION 1'
Since the tank trailers contents are limited to loi enriched uranium solutions f rom unirradiated sources, no shielding is necessary.
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6-1 Rev. O March 27, 1981
6.0 CRITICALITY EVALUATION
The criticality safety of the tank trailer is based on safe concen-tration.
The controls necessary to maintain a safe concentration have been explained in Sections 2.6 and 2.7 6.1 Discussion and Results The insulation surrounding the tank is the only design feature of.the tank trailer that provides for criticality control.
The effictiveness of the insulation has been demonstrated in Section 2.9, Appendix A and B.
This design feature plus.the administrative controls detailed in section 2.6.2 provide adequate criticality control.
Since a shipment will always consist of one tank trailer, designating the shipment as Fissile Class III with a limit of one package per ship-ment would be appropriate.
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7-1 n,
Rev. O March 27, 1981 7.0 OPERATING PROCEDURES 7.1 Procedure for Leading the Package Operating procedures for the tank trailer will detail the following requirements prior to leading:
a.
Inspect the tank to insure it is empty and clean, b.
Remove drain caps on drainer pans and inspect for leakage.
c.
Inspect spill tank for solution.
d.
TagetemperatureofUNHandinsurethattemperatureis e.
68 F or greater.
f.
Document all checks and inspections.
After loading the tank trailer:
a.
Clean the spill box.
b.
Inspect spill tank.
c.
Install new teflon gaskets.
d.
Inspect all bolts on flanges and manhole.
e.
Check retainer pan for leakage and replace drain caps.
f.
Document all checks and inspections.
In addition, the operating procedures will require that the containment tank be tested every 24 months in accordance with DOT specification MC-312 and ASME specifications including a 55 PSIG hydrostatic test.
7.2 Procedure for Unioadino the Package Procedures for unloading the tank trailer will include the same checks and inspections as described in Section 7.1.
7.3 Preparation of an Empty Package for Transport Procedures for preparation of an empty tank trailer for transport must include provision to insure that the tank, retainer pans, and spill tank are empty, i
8-1 Rev. O March 27, 1981 8.0 ACCEPTANCE TESTS AND MAINTENA"CE PROGRAM This chapter discusses tne acceptance test and maintenance program to be used on the packaging.
8.1 Acceptance Tests 8.1.1 Visual Inscection The containment tank will be visually inspected for alignment of vessel parts, tilt and orientation of noz:les.
This inspection is made to insure that no damage had occurred during fabrica-tion.
Defects found will be followed by more extensive exami-nation such as additional x-rays.
8.1.2 Structural and Pressure Tests The containment tank will be hydrostatically tested at 55 PSIG for a minimum of one hour.
This pressure test insures that the tank is leak tight.
If leaks are detected rewelding or re-working of parts will be required.
8.1. 3 Leak Tests The retainer pans and spill tank will require a water tightness test.
These units n.ust stand full of water for a minimum cf four hours.
Lestate will be corrected by rewelding or replace-ment of parts.
3.1.4 Comocnent Tests 8.1.4.1 Ruoture Disc The rupture disc used will be a standard off the shelve item with no additional testing required.
I 8.1.4.2 Gaskets The teflon gaskets are tested during the hydro-static test described in Section 8.1.2.
8.2 Maintenance Prooram 8.2.1 Structural and Pressure Test The hydrostatic test described in Section 8.1.2 must be per-formed every two years.
The test must be authorized by a certi-fied pressure vessel inspector.
If leakage occurs corrective
. measures must be followed by an acceptable retest prior to
)
further use of the tank trailer.
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, +. s Rev. O March 27, 1981 i
I 8.2.2 Leak Tetts Checks for leaks are made prior to each shipner.t of the tank trailer.
If the detection of leakene results in repair to the containment tank the hyderstatic test described in Section 3.2.1 must t:0 performed.
8.2.3 Subsystem Maintenance The trailer is maintained in accordance with gtneral industry standards.
The trailer is inspected for road worthinecs prior to each use, and any maintenance reouired as a result of the inspection is performed before the tank trailer is used.
8.2.4 Rupture Disc and Gaskets on Containc. cat Vessel The r!.pture disc is removed every L.co years during the h'dro-static test.
The disc is replaced if any sign of corrosion or wear is otserved.
Gaskets are replaced whenever flanges are removed or if leakage occurs during the hydrostatic test.
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