ML20197E161
| ML20197E161 | |
| Person / Time | |
|---|---|
| Site: | 07109071 |
| Issue date: | 01/07/1986 |
| From: | ANEFCO, INC. |
| To: | |
| Shared Package | |
| ML20197E154 | List: |
| References | |
| NUDOCS 8605150182 | |
| Download: ML20197E161 (25) | |
Text
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REMOTE HANDLED TRANSURANIC WASTE t
~
CASK AP-101 LICENSE AMENDMENTS CERTIFICATE OF COMPLIANCE # 9071 4
Dated: January 7, 1986 i
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REMOTE HANDLED TRANSURANIC WASTE CASK AP-101 LICENSE AMENDMENTS TABLE OF CONTENTS
0.1 INTRODUCTION
1.1 CANISTER DESCRIPTION 1.1.1 CANISTER SHAPE 1.1.2 CANISTER DIMENSIONS 1.1.3 CANISTER WEIGHT 1.1.4 CANISTER MATERIALS 1.1.5 CANISTER INTEGRITY 2.0 CANISTER DESIGN CRITERIA 2.1 WEIGHT AND DIMENSIONS 2.2 WASTE PACKAGE CONFIGURATION 2.3 MATERIALS 2.4 STRUCTURAL INTEGRITY 2.5-DESIGN LIFE 2.6 INTERNAL PRESSURE & GAS GENERATION 2.7 LEAK RATE 2.8 CANISTER DECONTAMINATION 2.9 INTERFACES 3.O CANISTER EVALUATION 3.1 CONTENTS OF PACKAGE 3.2 THERMAL EVALUATION 3.2.1 PACKAGE CONDITION & ENVIRONMENT 3.2.2 PACKAGE TEMPERATURE 3.2.3 EVALUATION
SUMMARY
3.3 CONTAINMENT 3.3.1 PRIMARY VESSEL 3.3.2 SECONDARY VESSEL 3.3.3 PRESSURIZATION OF CONTAINMENT 3.3.4 GAS GENERATION IN RH-TRU WASTE
'3.4 EVALUATION
SUMMARY
4.0 AP-101 CASK CONSIDERATIONS 4.1 HYPOTHETICAL RELEASTE CONSIDERATIONS 4.2 CASK DUNNAGE 5.O WASTE FORM
-5.1 CHART A - TYPICAL ISOTOPIC COMPOSITION &
CONTAINED ACTIVITY IN 55-GALLON DRUM
LIST OF DRAWINGS Drawing Number Description H-2-91273-1 RH-TRU WASTE CONTAINER ASSEMBLY H-2-91273-2 RH-TRU WASTE CONTAINER ASSEMBLY SZ-5 DUNNAGE FOR AP-101 CASK C
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0.1 INTRODUCTION
The purpose of this amendment to the AP-101 Certificate of Compliance Number 9071, is to include the waste form of defense RH-TRU* waste in the section on allowable contents as specified in the Certificate of Compliance.
The waste form (RH-TRU) will be contained in carbon steel canisters.
The physical description, integrity and quality control of these canisters are made part of this submittal.
The loaded canister will not exceed the 10,000 lb. allowable weight under the Certificate of Compliance.
The submittal presents all parameters which would potentially impact on the AP-101 cask under normal and hypothetical accident conditions in accordance with 10CFR71.
It is shown that there are no adverse effects upon the. structural integrity of the cask, heat transfer, or shielding.
- Remote Handled Transuranic i
i
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I 1.1 PRIMARY CANISTER 1.1 Canister Description 1.1.1 Canister Shape The shape of the canister will be a right angle cylinder.
1.1.2 Canister Dimensions Two engineering drawings of the typical canisters proposed for the shipment of RH-TRU waste are enclosed as Attachment I and II.
Typical drawings show that the canisters will be fabricated of carbon steel.
Canisters will be 26 inches outside diameter and 10'1" long.
The canister will be braced by dunage to prevent dynamic motion within the cavity.
I I
1.1.3 Canister Weight The empty canister will weigh less than 1000 lbs.
I and filled canisters will weigh less than 10,000 lbs. when filled with RH-TRU waste.
Since the weight of the canister with contents will not f
exceed 10,000 lbs which is the limit as defined in tha Certificate of Compliance Number 9071, it can be contained within the AP-101 cask.
f 1.1.4 Canister Materials
[
The materials of construction will be carbon
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steel.
1.1.5.
Canister Integrity The canister structural integrity will be suffi-cient to withstand routine operations, conditions for Type A shipment (reference 49CFR173.398).
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CANISTER DESIGN CRITERIA 2.1 Weight and Dimensions The typical canister diameter shall be nominally 26 inches (0.66m) and shall not exceed 121 inches (3.07m) in length including the pintle.
The canister weightdvdl be the minimmn achievable while meeting l
t other applicable criteria.
2.2 Waste Package Configuration All RH-TRU waste package external surface shall be.a smooth-sided cylinder and shall not have protrusions beyond the nominal outside diameter of the canister.
The handling appurtenance dv01 be a pintle, shown in Figure 1, welded at the top centerline of the package.
2.3 Materials The canister body,_end caps and pintle shall be fabri-cated from carbon steel.
The external surfaces shall be coated with acryllic enamel or other anti-corrosion coating.
If material other than carbon steel are used for sealing, filtered vents, etc., they shall be compatible with carbon steel.
2.4 Structural Integrity The canister structural integrity shall be sufficient to withstand routine operating conditions, conditions for Type A packaging and retrieval after storage. The environmental and test conditions for Type A packaging are as follows:
2.4.1 Standards for Type A packaging:
1.
Type A packaging must be so designed and constructed that, if it were subject to the environmental and test conditions prescribed in this paragraph; (1) There would be no release of radioactive material from the package; (11) The effectiveness of the packaging would not be substantially reduced; and-(111) There would be no mixture of gases or vapors in the package which could, through any credible increase of pressure or an explosion, significantly reduce the effectiveness of the package.
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2.0 cont.
2.4.1 cont.
2.
Environmental conditions:
(1) Heat. Direct sunlight at an ambient temperature of 130*F in still air.
(11) Cold, an ambient temperature of -40'F in still air and shade.
(111) Not Applicable (lV) Vibration. Vibration normally incident to trans-portation.
3.
Test conditions:
The packaging shall be subject to all of the following tests unless specifically exempted there-from, and also to the consecutive application of at least two of the following tests from which it is not specifically exempted:
(1) Not Applicable (11) Free drop.
A free drop through a distance of 4 feet onto a flat essentially unyielding horizontal surface. striking the surface in a position for which maximum damage is expected.
i (111) Not Applicable (lV) Penetration.
Impact of the hemisphereical end of a vertical steel cylinder 1% inches in diameter and weighing 13. pounds dropped from a height of 40 inches onto the exposed surface of the package which is expected to be most vulnerable to puncture.
The long axis of the cylinder shall be perpendicular to the package surface.
(V) Not Applicable 2.5 Design Life The RH-TRU waste canisters including labeling shall have a design life of 25 years.
2.6 Internal Pressure & Gas Generation The canister shall have provisions for continuous venting of gases through a HEPA type filter under normal conditions.
2.7 Leak Rate The gas pressure drop leakage test or equivalent shall
.be used to demonstrate the final closure seals effective-ness of the RH-TRU waste canister.
The filter shall be closed during this test.
The test shall be_ conducted' s..
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2.7 cont.
in accordance with requirements in ANSI N14.5, "American National Standards for Leakage. Tests on Packages for Shipment of Radioactive Materials".
2.8 Canister Decontamination The outside of the canister shall be designed to facilitate surface decontamination and cleaning.
2.9 Interfaces Coordination with the following interfaces shall be i
maintained to assure that the waste canister design and the interfaces are compatible:
(1) empty and full canister handling and storage system, (2) filling equipment and procedures, (3) sealing and inspection equipment, (4) handling and transporting systems, and (5)the handling, transporting, emplacement and retrieval systems.
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3.0 CANISTER EVALUATION 3.1 Contents of Package The waste material to be contained in the canister will be of the solid contaminated matrix type-3.2 Thermal Evaluation The RH-TRU waste material that will be shipped will have different decay heats associated with it.
For that. reason evaluation was performed to evaluate the temperatures an that would prevail for total decay heat generation of 300 and 1000 watts per package.
3.2.1 Package Conditions and Environment It is assumed that in addition to the decay heat, the package is exposed to an environment of 100'F where the cask absorbs 400 cal /cm2 as specified in 10CFR71.71 under normal conditions.
3.2.2 Package Tenperature Assuming the following thermo-physical properties.
of the materials of construction of the cask exist at steady state:
Material k (BTU /hr-f t'F Stainless Steel 11 Lead 63 Fire shield air gap 0.233 equilibrium TheAtemperatures of the surface of the AP-101 cask, the temperature of the air in the AP-101 cask void, and the temperature of the proposed canister surfaces were. calculated assuming the ambient air temperature is 80 F.
Temperature (*F)
Decay Heat AP-101 Surface AP-101 Air Canister
. Surface 300w 82.3
-92.4 98.1 1000w 89.4 120.3 140.1 Under the environmental' conditions specified in 10CFR71.71 where the cask will be ex sed for 12 2
hours to 400 cal /cm2 or 929 BTU /ft ' the maximum equilibrium temperatures increased by 69.l*F.
3.2.3 Evaluation Summary The temperatures that will exist in the package were calculated above.
Under normal operating conditions at ambient temperatures, the surface temperature of the package will vary.from 98*F to 140*F for decay heat loads varying between 300 and 1000 watts.
The contents of the packages are stable and will not be affected at these temperature conditions.
Even under exposure to 100'F and a solar load of 400 cal /cm2 the equilibrium temperatures will be less than 210'F and will not exceed values under which the contents of the packages would be affected.
3.3 Containment 3.3.1 Primary Vessel As indicated in Section 2.2 under the design criteria for the primary canister, a gas pressure drop leakage test will be conducted in accordance with the requirements of ANSI 14.5 to demonstrate that the final closure seals of the RH-TRU canister are effective.
The canister is equipped with a HEPA type filter which will retain all solids and permits venting of gases should venting be necessary.
3.3.2 Secondary Vessel It has been shown in.the AP-101 Safety Analysis Report that the maximum leak rate during accident conditions would be (3) three cask volumes per 4 curies,.which would hour assuming a content of 10 release approximately 0.9 x 10-6 #01/ min.
If such a leak rate were to occur for a one week time interval, the total release of activity would be
-3 0.9 x 10-6 3Ci 440 min 7 days 9x 10 pCi min day week week The A value f r Pu 239 is 0.002Ci.
Therefore, the 2
j containment capability within the AP-101 cask exceeds the requirements gf 10CFR71.51 with a safety factor of 2.2 x 10.
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3 3.3.3 Pressurization of Containment It.is-assumed that an overpressure of.300 psig, produced by. the' RH-TRU, waste,',is;imposediMOtEisi.
i AR-1013 cavity.
I This pressure will be contained within'the cask by the. inner ~shell, which will be braced,by the lead and.-the outer shell as well.as byythe upper s
plate and 20 1 " - 12UNF x 2 " long hex bolts.
t considering the inner shell as the pressure vessel, the primary membrane stress is:
(Roark & Young p.448, case Ib) l Sm=
= 300' psi 0 6 5 in
= 6720 psi-4 Considering the bottom cavity plate as a simple i
supported plate, the maximum stress is:
(Roark & Young p.'
363, case 10a) 2 P
S,= 6(0.206)
= 1236(300) psi. (2 06 5) i S,= 17,085. psi.
The closure lid, which.is thick'er, will have even lower stresses.
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5 The twenty closure bolts will have to resist a load imposed by the 300 psi pressure on the 28" diameter cavity.
The pressure stress will be:
2 2
( W' ) (14 ) ? in.
300 psi 6077 psi g
B 2
20 x 1.52 in
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At a temperature of 100*F,.the allowable primary--
membrane stress.is 20,000 psi (as shown in Table l'.3-1 of'the AP-101 SAR).
The allowable membrane l
plus bending stress is 28,000 psi and the; allowable-stress in the bolts is 105,000 psi.
l These values 1 exceed the calculated values of.6720 4
psi.for the membrane stress, 23,800 psi for.the membrane plus bending' stresses, and 6080 psi for the bolt stress.
.Therefore,.the cask cavity may withstand the 300 psi specification requirements of RH-TRU shipments.
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3.3.4 Gas Generation in RH-TRU Waste Introduction g
The generation of gases, including hydrogen, in TRU wastes has been studied extensively.
In this evaluation, appropriate data from the literature i
has been applied to the packaging and transporta-h tion system for RH-TRU waste in the AP-101 cask.
l The rates of total gas and hydrogen genmation with-
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in the RH-TRU waste have been calculated, as have the pressure consequences of such an occurrence-ll Vithin the RH system.
For this evaluation, it is assumed that waste containers are overpacked into DOT 17C 55 gallon drums.
Three 55 gallon drums will fit into a 26" O.D. x 121"long waste canister which in turn will l
fit into the 28" ID AP-101 shipping cask.
l k
The waste canister design includes a filtered vent, and the interior containers, including the 55 gallon drums, are not pressure tight.
Therefore, i
no pressure barrier exists between the actual waste 7
and the AP-101 cask which is assumed to be pressure-tight for this evaluation.
s Gas Generation Mechanisms The gas generation mechanisms,used in this evalu-ation, as identified in the literature, include i
radiolysis, bacterial decomposition, thermal de-gradation and corrosion.
The radiolytic gas generation rates are given by:
Rate = A x F xf x G Where A = Total Activity for Radiation type under Consideration q
F = Average Energy per Disintegration (MeV/ dis) f = Fraction of energy absorbed by material j
G = Number of Gas Molecules Produced per
_100eV. absorbed i
For Alpha radiolysis, assuming that 1000 Ci at an average energy of SMeV and a G value of 1.4 are 2
present in a load, 1.55 x 10 moles /hr are generated.
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t 3.3.4 cont.
For Beta radiolysis of water and hydrocarbons, assuming that 900 Ci at an average energy of l
0.28MeV and a G value of 0.45 for water and 1.4
'for hydrocarbons are present in a load, 7.6 x 10-4 moles /hr are generated.
Assuming a maximum temperature of 100'C, it can be estimated from the literature that 1.5 x 10-2 moles /hr are generated by thermal degeneration.
Bacterial and corrosion gas generation are not credible or measureable for the conditions assumed above.
The gas generation by the above mechanisms have been estimated to be about 3.14 x 10-2 moles /hr.
Pressure Build-up In order to determine a pressure build-up, it is necessary to assume a void volume which will be present in the containers, the drums, the canister, and the transportation cask.
For this conservative evaluation, it was assumed that 50% of the drum volume was void, and that there is a 0.5 inch clearance between the transport cask and the canister.
The absolute pressure in the cask at any time is:
,Po [n +5t] Tt o
p Uo To Where P = Absolute Pressure n = Number of moles
$ = Gas Generation rate.(moles / time)
T = Absolute Temperature t = elapsed time sub o= at time 0 sub t = at time t assuming that T
= 298'K, Tt = 373*K, Po = 14'.7 psia o
i 3.'3.4 cont.
l
-2 and that the gas generation rate is 3.14 x 10 j
moles /hr The absolute pressure in the cask will be 33.1 psia after one month and 19C 6 psia after one year.
Calculations were performed for the capability of the AP-101 cask to contain RH-TRU waste under pressure.
Those calculations showed a capability to retain a pressure build-up of 300psig, which will be extremely conservative when'it is considered that it would take a year tx) reach a pressure less than 200psig. (Ref. 3.3.3)
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3.4 Evaluation Summary It is shown in 3.3.1 above that the primary vessel is designed to retain all-solid RH-TRU wastes that will be loaded into the canister.
The canister is vented through a HEPA filter which will release the gases should gasc:
gelease occur.
In Section 3.3.2, it is shown that the design of the AP-101 cask will release less than the allowable A2 quantities of radioactivity.
Section 3.3.3 demonstrates that the design of the AP-101 cask is capable of resisting a pressure'of 300 psig which is the maximum pressure to be released from the RH-TRU canister.
Consequently, the combination of the RH-TRU waste canister packaged in the AP-101 transport cask provides adequate containment for the RH-TRU waste.
4.0" AP-101 CASK CONSIDERATIONS 4.. l. -
Hypothetical Release Considerations The AP-101 cask wfDJbe sealed and leak tested to assure that there is no leak, using a detector with a minimum sensitivity of 1 x 10-3atm Mr C
in accordance with ANSI 14.5.
If it is assumed that a leak occurs during a transport, at a rate of 1 x 10-3 cc the total leak for a duration of one week will be:
5 sec cc 10-3 c x
6.048 x 10
= 604.8 see wk wk The maximum activity that will be transported in the AP-101 cask will be 1000Ci.
It has been shown* that only 0.5% of the RH-TRU waste activity is present as leakable, respirable fines.
Further, the canister vent HEPA filter has 99.7%-
efficiency factor for 0.3u particulate.
Combining the above factors, the total activity that will be available to the cask interior will be:
1000Ci x 5 x 10-3 x 3 x 10-3 = 0.015Ci The volume of the canister, which has a 26"OD and is 121" high is:
3 77 (26")2 (121")
= 37.18 ft 4
1728 The volume of the AP-101 cavity, which is 28"ID and 167" high is:
3 7f(28")2 (167")
= 59.51 ft 4
1728 Given the total activity of 0.015Ci is distributed in the void volume of the cask, the concentration of activity is:
3 4 cc 5
(59.51 - 37.18)ft x 2.832 x 10
= 6.32 x 10 cc 0.015Ci
= 2.37 x 10-8 Ci 5
cc 6.32 x 10 cc for a duration of one Assuming a leak rate of 1 x10-3 cc week, the total activity thatwouf8 be leaked is:
-8 i
-5 C 604.8[x2.37x10
= 1.43 x 10 cc
- Warrant, M.M., " Report of the RH-TRU Characteristics Interface Working Group", April 30, 1985.
i Assuming a most restrictive A value of 0.002, a safety j
2
-3 f.j3
= 140 is available.
factor of 6
10-3 4.2 '
Cask Dunnage The nominal RH-TRU canister dimensions are 26"OD x 121" i
long. (Ref. Dwg.). This canister will be positioned in the AP-101 cask whose cavity dimensions are 28" ID x 167" long.
Calculations have been performed to assure that l
the potential energy developed by the movement of the canister during transportation of the canister within the cask will be absorbed by an. installed buffer and will not affect the cask.- For that purpose, a cylinder, fabricated from a honeycomb material will be' installed j
in'the AP-101 cask to absorb the eno.gy.
The maximum weight of the canister (in conformance with the AP-101 Certificate of Compliance) is 10,000 lbs.
The maximum distance that the canister can travel within the AP-101~ cask is the difference between the length of 1
the cavity and the length of the canister.
The maximum-acceleration that the canister will attain >is 10g along-the direction in which the package travels,_ equivalent to the standard applied for tie-down forces in 10CFR 71.45, thus the maximum energy that could be developed would be:
3 10 x 10,000 lbs x 46 in. = 4,600,000 in-lbs.'
l The stress required for the deformation of the honeycomb material that.will be employed is 1600fft/in.
Given the OD of the honeycomb cylinder as 27.5. inches, I
then the energy absorption capacity of such a cylinder is:
(27.5)2'in x:1^ inch = 950,300in[1b 1
2 g2/in. x 1600 The maximum potential energy of the canister would there--
fore, be absorbed in 00 000
= 4.84 inches 99 or less than.5 inches of a 27.5-inch diameter' cylinder.
of honeycomb material..~A 45" long cylinder which will be installed to serve as dunnage,.will limit the movement
~
of the RH-TRU canister and will have. excess. capability to absorb any potential energy developed. ( Ref.-DWG SZ-5) l 1
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5.0 WASTE FORM The waste form nuclides and average qualitative description is included in this submittal (Chart A).
The waste as described is defined as transuranic waste (Rll-TRU, remote handled transuranic waste) and is characterized by those radionuclides which are so indicated.
The principal acti-vities (nuclides) are indicated on the chart.
Samples of DOE waste were analyzed at the major facilities to establish the norm.
The A2 factor for the worst case hypothetical accident and the WIPP waste acceptance criteria (WIPP-WAC) were used to postulate release rates.
Reference Section 3 of this submittal.
Those isotopes which could be potentially present in a canister are defined as follows:
TRU:
Am-241, Cf-249, Cf-250, Cf-252 Cm-243, Cm-245, Cm-246 Pu-239, Pu-240, Pu-242 U-233 non-TRU:
mixed fission products Sr-90, Ac-227, Pa-233
'?,
7 5.1 CHART A TYPICAL ISOTOPIC COMPOSITION & CONTAINED ACTIVITY IN SS-GALLON DRUM
- Gross Weight:
50 kg NUCLIDE A. (Ci)
MASS (g)
ACTIVITY (Ci) 7 Am 241 0.008 2.7 E-4 9.1 E-4 Cf 249 0.002 3.9 E-10 1.6 E-9 Cf 250 0.007 3.8 E-10 4.2 E-8 Cf 252 0.009 3.9 E-9 2.1 E-6 Cm 243 0.009 2.2 E-6 9.9 E-5 cm 245 0.006 3.9 E-5 6.8 E-6 cm 246 0.006 2.7 E-3 8.3 E-4 Pu 238 0.003 3.8 E-5 6.6 E-4 Pu 239 0.002 2.3 E-2 1.4 E-3 Pu 240 0.002 5.6 E-3 1.3 E-3 Pu 242 0.003 8.4 E-5 3.0 E-7 U
233 0.03 2.0 E-7 1.9 E-9 TRU Waste Concentration: 140jiCi/kg J.E. Bigelow to T. Grizzard - ORNL Intra Lab Memo Dated October 23, 1984.
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