ML20125B541
| ML20125B541 | |
| Person / Time | |
|---|---|
| Site: | 07104960 |
| Issue date: | 10/31/1979 |
| From: | Roeder J ENERGY, DEPT. OF |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 14583, NUDOCS 7911280263 | |
| Download: ML20125B541 (28) | |
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OCT 3 1 1973 91
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Charlos E. MacDonald, Chief Trent,portation "rench
/p Division of Fucl Cycle and q
g Material Safety Nuclear Regulatory Cconission Uanhing, ton, D.C.
20555
Dear Sir:
This refers to your letter of May 31, 1970 regarding IIRC review of the Model LLD-l pachat;e, USA /4960/BF.
The information requested in referenced letter is fa mardeJ in the cnclosurco hereto.
.1 m 4
Jack R. Roeder, Director UCR:::LB Operr.tiens1 Safety Division
Enclosures:
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N W, e. 00V E R N M E ta t P ales TIN J C FACit I G 74.f 14 4 66
c M E M O R'A N D U M i
.r July 17, 1979 l
I TO:
W. R. KENNEDY, JR., 723-A FROM:
D. J. PELLARIN j
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IhTORMATION FOR NRC REVIEW OF THE LLD-1 PACra0E i
INTRODUCTION j
The Nuclear Regulatory Commission (NRC) is conducting a review of the i
LLD-1 shipping packagel for the Albuquerque Operations Office of the Departme'nt 2
of Energy (ALOO-DOE) who issued the current Certificate of Compliance.
In connection with their review, NRC has requested the following information per-tinent to use of the LLD-1 for shipment of Pu Metal *:
1.
Verification that the outer conrber (bird) remains attached within the outer tubular framework (bit cage) of the package following the 3
30-foot free fall drop test of the hypothetical accident sequence,
with the package oriented to impact on the bottom.
Earlier drop tests 1
at SRP in support of the Safety Analysis Report for the LLD-1 were designed to impact the package on its top.
2.
A description of the leak testing and maintenance programs to ensure the containment capability of the LLD-1.
3.
A description of the radiographic examination that was used to assure that the specification for a full penetration weld had been satisfied in the initial fabricatit.a of the Spec 2R4 containment vessel.
These NRC questions concerning the LLD-1 were directed to the Shipping Container Development Group of the Equipment Engineering Department (EED).
The purpose of this memorandum is to present the results of tests, analyses and investigations that will provide a response to each of the NRC questions.
The LLD-1 does not satisfy current containment regulations for shipment of I
large quantities of Pu oxide. Therefore, all of NRC's questions are inter-preted to apply solely to the use of the LLD-1 for Pu metal.
1 1
i 90009301 1
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SUMMARY
The major responses to NRC questions concerning the LLD-1 package are summarized below:
Drop tests desi aed to investigate the structural integrity of the LLD-1 o
t package, given a bottom drop orientation in the 30-foot free fall, dem-onstrated that the containment vessel is retained within the tubular framework.
o KENO-IV calculations, based on the premise that the containment vessel can be displaced anywhere within the bounds of the outer frame, produce criticality limitations no more severe than those existing in the SARP tsainly because the SARP assumes a 25% reduction in the volume of th, package).
o Containment requirements for the LLD-1 have been quantitatively established and are sinmarized in Table V.
Leakage tests to assure the required degree of containment will be implemented.
Included is an initial fabrication containment verification test to be completed retroactively for all 2R vessels.
o Maintenance programs for the LLD-1 exist in current procedures and will be strengthened, based on improved closure techniques and assembly veri-fication leak tests.
o Radiographic inspections and quality assurance reports exist for all Spec 2R vessels in use.
The testing was done by the Pittsburg Testing Laboratory and weld integrity was interpreted according to the ASME Code.
J DISCUSSION I.
Description of the LLD-1 Package The LLD-1 Package (Figure 1) consists of two concentric cylindrical i
vessels centered in a tubular steel framework.
The inner (Spec 2R) contain-er is a 1/2-inch-thick carbon steel cylinder with a 4 1/2-inch I.D. and a 10 1/8-inch inside height.
It is sealed by a threaded plug and silicone elastomer 0-ring.
The outer container is a carbon steel cylinder about 17-inches high with a minimum I.D. of 6 1/4-inches.
It is scaled with a bearing plate and metal 0-ring and is insulated from the inner container with refractory felt.
Both containers are centered in a 16x16x25-inch high framework of 3/4-inch 0.D. steel tubing and covered with a thin-gage per-forated aluminum sheath to prevent the entry of foreigh objects. The total weight of the package is 130 lbs.
The Pu metal buttons are individually crimp-sealed in a tinned steel r
can and heat-sealed within a polyethylene bag which in turn is crimp-sealed within a No. 3 steel can.
These cans are sealed within the 2R container as shown in Figure 1.
II.
Bottom Impact Drop Tests of the LLD-1 Packace Two 30-foot drop tests of the LLD-1 package were performed at SRP in i
19741 as part of the hypothetical accident sequence of 10 CFR 71.
In both tests the packages were oriented to impact on the top in a geometry
,.e
~~ _
_ _ _ v judged to produce maximum damage to the locking lugs of the outer container.
In one test, a break occurred at the bottom of one of the curved steel tubes that support the containment vessel; in the other test', a break occurred in the tubular ring of the lid handwheel assembly.
In both cases a small amount of buckling occurred in the aluminum basket with no significant de-crease in the volume of the package.
The overall damage f rom both drops was judged to be superficial and without adverse effect on shipment safety.
Two additional drop tests were performed to provide information to NRC for their evaluation of the LLD-1 package.
In these tests representative LLD-1 packages were subjected to a 30-foot free fall with bottom impact onto an unyielding surface.
The most severely damaged package was subsequently subjected to the additional structural stresses of the hypothetical accident, viz. the puncture test and the thermal test.
The drop tests were completed during December,1978 by Reactor Physics Division personnel in Building 777-M.
Descriptions of the tests are summarized below:
Tast of LLD-1 No. 116 On December 4,1978, the 2R primary container of LLD-1 No.116 cas filled with 35 pounds of lead shot (maximum loading of Pu metal au-thorized in the SARP is 9.9 lbs.), and the top plug was screwed into place to engage the 0-ring seal.
The secondary container insulation and lid were replaced. An adapter was attached to the top of the package and connected to a quick release mechanism supported by a 1-ton crane (Figure 2).
Af ter verifying that the bottom of the pack-age was horizontal, the LLD-1 package was positioned over the floor opening for the 30-foot drop.
It was impacted onto a flat 8'x8'x1/2" steel plate bolted to a 4-foot-thick reinforced concrete floor.
Due to a slight sideways impulse by the release device, the LLD-1 package hit on one side of the bottom with an approximate 5 list.
j On that side, the top two members of the tubing holding the second-ary container necked to smaller diameters and snapped at the corner welds.
The same two pieces of tubing collapsed below the secondary container.
This side of the container dropped approximately 3-inches j
but did not reach the bottom of the outer aluminum mesh f ramework.
The opposite side of the secondary container dropped approximately 2-inches as the two support tubes of the framework deformed.
The aluminum mesh and framework remained intact although slightly warped.
(Figure 3).
Test of LLD-1 No. 123 On December 7,1978, the primary container of LLD-1 No. 123 was filled with 14.5 pounds of lead shot and the top plug screwed into place to engage the 0-ring seal.
The secondary container insulation and lid were replaced.
The suspension system was improved to ensure a clean release by use of a flexible cable (Figure 4).
The adapter plate was attached and leveled, then the package was dropped 30-feet.
The bottom of the package hit flat (Figure 5).
The upper ends of all four of the tubing supports for the containment vessel broke loose at the welds in the corners (Figure 6).
The containment vessel was displaced downward approximately 4-inches but did not reach the outer aluminum mesh on the bottom (Figure 7).
The bottom ends of the four vupport tubes collapsed and two welds fractured at their corner post attachment (Figures 8 and 9).
No noticeable change in the overall volume of the package occurred.
1 90009303
__ _ t On December 15, 1978, the LLD-1 packages next were subjected to the punc-ture test of the hypothetical accident condition sequence of 10 CFR 71 in an effort to aggravate the damage incurred in the 30-foot drop test.
The packages first were dropped in the bottom orientation in a free drop of 40-inches onto a 6-inch diameter,10-inch long steel bar mounted on an essentially unyielding horizontal surface. A subsequent drop was made with impact on the top of the outer hand ring of the containment vessel.
The bottom drop of the LLD-1 No. 123 package resulted in an additional N -inch downward displacement of the containment vessel.
Tbe top drop did not produce any further displacement of the containment vessel since the impact energy was dissipated in bending the cross bar of the outer hand ring.
The LLD-1 No.123 package was subjected to an exaggerated version of the fire test in the hypothetical accident sequence. On January 5,1979, af ter removal of the outer perforated aluminum basket, the LLD-1 package was in-troduced on its side into the furnace of the SRL Fabrication Laboratory.
Over a 4-hour period the furnace temperature was increased from room tem-perature to 800 C where it was maintained for 30 minutes and then the fur-nace was de-energized. The package remained in the furnace as it slowly cooled over a 2 -day period.
The tubing support frame for the containment vessel sagged at the remaining intact welds during the fire test and the containment vessel tilted until the upper ends of the broken tube supports contacted the outer tube f rame-work (Figure 10).
At the conclusion of the testing program, the containment vessel was still retained within the outer frame of the LLD-1 package.
However, the 30-foot bottom end impact, free fall drop test had produced more extensive structural damage to the tubular steel support f rame tean had occurred in the 1974 SARP tests.
The subsequent thermal stress test cauced the containment vessel to tilt within the outer frame.
III. Criticality Re-Evaluation of the LLD-1 Package In conjunction with the new structural tests of the LLD-1 package,5 H. K.
Clark of SRL completed a criticality re-evaluation of the LLD-1 package, A series of calculations using KENO-IV with Hansen-Roach cross sections were performed for configurations representing geometrical extremes suggested by the new tests of the LLD-1.
Three configurations were studied. In each, a 4.5 Kg spherical mass of Pu metal was assumed to be displaced to the bottom of the 2R containment vessel.
No reduction in package volume was assumed since neither previous nor present tests indicated any.
The dimensions of the calculational model are those of the tubular steel f rame.
The outer perforated aluminum box adds about 10% to the volume of the package.
The 5%
decrease in the effective volume required in the criticality analysis is more than satisfied by use of the frame dimensions. No additional volume reduction is supported by the test results.
The cases studied were:
(1) A fully reflected (H O) 8 x 8 x 8 array in which the containment vessels 2
in the top 8 x 8 x 4 layer are displaced to the bottom of the outer frame of the LLD-1.
The bottom 8 x 8 x 4 layer is a mirror image of the top layer.
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1 (2) A fully reflected (H O) 8 x 8 x 8 array in which the top 8 x 8 x 1 2
layer has containment vessels displaced to the bottom. The next layer is a mirror image. The next 2 layers duplicate the top two and so on, so that four pairs of planes with units at the minimum possible vertical spacing are formed.
(3) A fully reflected (H O) 8 x 8 x 8 array identical to the second con-2 figuration except that the containment vessels are displaced horizontally into adjacent corners so that clusters of 8 closely spaced units are formed.
Results for the three cases are given in Table I.
Three degrees of satura-tion of the mineral felt insulation between the inner and outer containers were assumed.
Table I.
LLI)-1 Reactivity for Hypothetical Configurations acdon H O h Feh fr lume 2
Configuration eff 0
0.5 1.00 1
0.903 0.005 0.902 0.006 0.901 0.007 2
0.912 0.005 0.901 0.007 0.895 1 0.005 3
0.935 0.006 0.935 0.005 0.930 0.005 The results in no case are significantly more reactive than those obtained for i
the hypothetical accident case represented by a 257. reduction in volume i
contained in the current LLD-1 SARP.
The effect of varying the moisture content of the insulating felt is not significant.
IV.
LLD-1 Containment Requirements Conservative analysis of maximum permissible leakage rates assumes that j
some Pu02 may be present and is more likely to escape containment than metal particles. Package containment requirements for Type B (M) packages not de-signed fcr continuous venting (such as LLD-1) are to restrict the loss of radioactive contents to less than A x10-6 per hour following the normal con-2 dition testing of 10 CFR 71-Appendix A and to less than A2 in 1 week j
following the accident conditions testing of 30 CFR 71-Appendix B.
A minimum A2 value of 24.6 mci was determined for a worst case admix of Pu isotopes within the specification limits for weapons grade Pu.
Since the weighted average specific activity of the mixture is 1.17 C1/gm, the mass of Pu associated with the A2 limit is 21.2 mg or 24.0 mg of Puo2 Utilizing this value, the maximum permissibic leakage rates of Puo2 for normal and accident conditions of transport become 2.4x10-8 gm/hr and 2.4 x 10-2 gm/1 week respectively.
V.
Maximum Permissible Helium Leakage Rates For the 2R Vessel L. C. Schwendiman, et al have measured helium and Pu02 (fuel grade) leakage rates through " standard leaks" incorporated into a container.
The on-going experimental program is investigating Icakage rates as a function of pressure, orifice size, container orientation, temperature and vibration.
Results summarized in their Oct. 1-De c. 29, 1978 Quarterly 6
Progress Report are duplicated below in Tables II and II.
wo s t of data are given, identified as replicate 1 and replicate 2, corresponding to two chronologically dif ferent experimental campaigns.
Results are reported as the arithmetic mean of the He atom to pug 2 molecule leak ratio.
The difference between cell means is statistically significant in only a few of the many possible cell comparisons.
Since there is no consistent, observable correlation associated with position, vibration or orifice size, the data in Tables II and III have been further collapsed by arithmetic averaging.
The reduced data given in Table IV reflect the significantly lower ratio value for the ambient pressure case. Increasing pressure from 440 psig to 920 psig has no significant effect on the correlation.
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TABLE II ARITIIMETIC MEAN VALUE OF He ATOM: Pu02 MOLECULE RATIO AND THE STANDARD DEVIATION FOR EACll EXPERIMENTAL CONDITION (MEAN / STANDARD DEVIATION) (REPLICATE 1)
Position-t.p sideways Down Pressure:
140 920 440 920 440 920 M'I C'i t
,, py in,
_ psig _ _
ktaient
- _pg_,
psig
_ _ An.bient
__ g il_
_ p g _,_
with Vibrati011 H *I 1.2E9/9.0E6 2.5E9 8.9I3 1.6E9/3.5EB 3.2E 9/ 3.8E 9 5.4E8/2.1EH I
5-m Orifice 10 pm Orifice 7.BE4/2.8E4 1.4E4/2.8ts 4.6E9/5.7E9 h.5E>/9.2E5 1.4E9/2.ets 4.4E8/4.0E8 5.(+E8/4.3E8
<0..m Orifice 1.7E5/8.5E4 8.6l8/l.6E9 1.4LH/2.3E0 1.4E5/l.2E5 2.4fH/7.9E1 2.4E10/3.3E10 1.0L5 6.0E9/8.5E9 1.6E10/2. LEIO W i tlu.su t dit.retion 5..in Orifice 3.7F4/2.8E4 1.1E9/6.7E8 lu..m Orifice 1.bi4/1.3t4 4.6E8/5.5E8
.ite
.,u or i t ir e I.SES
- 2. 311./1.91 6
- 4. 3t h/ l. 31 u
- 3. 3E 5 6.7f9/4.2E9 1.0f9 1.2E5/1.0t5
- 2. 3E8/2. 3E 8
- 1. t.E 9/ 6. 4 E 8 (J ) Hissing Lt.(s ela t iori da ta ilue to hittiute am utit of I'uO dctetted g
Gs3 Cca0 E?e) o O
O W) 3?e) u O
(m)
N w
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4 f.
TABLE III
@I,TlDIETIC MEAN VALUE OF He ATOM: PuDh MOLECULE 1COR'RCLATION AND TIIE l
STANDARD DEVIATION FOR EACH EXPERIMENTAL CONDITION (MEAN/ STANDARD, DEVIATION)
MATRIX COMPLETION EXPERIMENTS (REPLICATE 2)
Position:
Up 00*"
Dru sure:
440 920 4:0 920 Ambient psio psic Anni et
- sta psic j
With Vibration S.8E3/7.lE3 2.5 E]/1. l E9 5-um Orifice 1.4E10/1.5E10 10.m 0-ifice J
1.5 Ell /2 IEll 2.CE6 4.JE9/1.8E9 l
20 u.n Orf fice 1.6E6/1.9E6
'ni tnou t vioration 5 s Orifice 2.5E4/7.6E3 M'
3.9E9/3 IE9 1.5E9/3.3E3 5.2E9/4.lE9 10 m Orifice i
20-um Orifice 1.2E6 1.4 Ell 5.6ES 1.2 Ell /1.2 Ell (a) Missing correlation data due to minute amount of FuC; detected 0)
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TABLE IV i
AVERAGE VALUES OF THE He ATOM:
pug 2 MOLECULE LEAK RATIO He ATOM PRESSURE,PSIC Pu09 MOLECULE LEAK RATIO Ambient Press 4.4 x 105 5 x 105 440 psig
- 2. 8 x le ' :,.98 x 109 10 920 psig 2.6 x 1010 1.2 x 10 90009309
)
Conservatively utilizing the He atom to Fu02 m lecule leak ratio value for ambient pressure the maximum acceptable Puo2 leakage rate of 10 2.4 x 10-8 gm/hr (1.5 x 10 molecules /sec) for normal conditions of 15 atoms /sec transport corresponds to a He atom leakage rate of 6.6 x 10 or 2.5 x 10-4 cm>/sec.
Conservatively adopting this leakage rate to applytothecasewherethepressuredifferentialis1atmosghere,one obtain a maximum acceptable helium leakage rate of 2.5 x 10-atm-cm3/sec for the 2R vessel (tested at 1.5 times the normal operating pressure or 30 psia).
3 A maximum acceptable helium leakage rate of 1.5 atm-cm /sec (tested at 33 psia) similarly is derived for the accident conditions of transport.
The post-accident containment test of the 2R vessel reported in the SARP for the LLD-1 was performed by the gas pressure drop technique.
In the test at 30 psig no pressure drop occurred over a 30 minute interval with a gage of 0.5 psi sensitivity.
The degree of leak tightness quantitatively established by the test was n 8.6 x 10-2 atm-cm3/sec.
The test that was performed meets the requirements established in this analysis for the 2R vessel considering the presence of oxide on the metal.
Containment requirements for the LLD-1 Package are summarized on Table V.
1 Table V.
Summary of LLD-1 Containment Requirements for Pu Metal Component Test Condition Regulatory Standard Test Standard 3
Spec 2R Vessel Normal Conditions of A2 x 10-6 per hour I 2.5 x 10-4 ato em /sec Transport (Appendix A at interior pressure of 10 CFR 71) of 30 psia Accident Conditions of A2 in 1 week t 1.5 atm cm3/see Transport (Appendix B at interior pressure of 10 CFR 71) of 33 psia VI.
LLD-1 Leakage Test Requirements A.
Containment System Fabrication Verification An initial fabrication containment verification test will be completed retroactively for all LLD-1 2R vessels (%150).
establish that the air leakage rate is 5 2. 5 x 10-4 atmem}hetestwill
/sec. with an interior pressure of 30 psia.
A proposed test procedure is outlined below.
Other methods may be investigated to accomplish the same objective.
1.
Invert the 2R vessel with the screw plug removed and flood with He gas.
2.
Place 10 gms of ice on the screw plug (with a new lubricated 0-ring in place) and quickly screw into place until tightly seated while maintaining the 2R vessel in the inverted position.
3.
Return the 2R vessel to the upright position and tighten the screw plug to achieve 20% compression of the 0-ring.
The compression will be established by depth measurements for each screw plug-2R vessel combination.
90009310 l-(
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4.
Wrap the outside of the 2R vessel with resistance heating tape.
5.
Install a thermocouple securely to the outside surface of the 2R vessel.
6.
Connect T/C and heater leads and install in the test stand of a calibrated He mass spectrometer leak test system.
7.
Evacuate system 8.
Increase the surface temperature of the 2R to 202 F.
9.
Establish equilibrium conditions and quantitatively measure the He leakage rate using a calibrated He mass spectrometer.
B.
Containment System Periodic Verification Each 2R vessel will be leak tested as in Part A af ter every third use and before actual use for shipment if it has not been tested within the preceding 12-month period.
C.
Containment System Assembly Verification As part of preparation for each shipment, the containment capability oftheLLD-1gackagewillbeverified.
The air bubble, vacuum and glycol method will be used to establish that the leak rate of the loaded and assembled 2R vessel is 5 10-3 atm cm /sec.
3 VII. Maintenance Requirements for the LLD-1 Package Maintenance requirements for the LLD-1 are embodied in DuPont Staadard Operating Logs (DPSOL).
DPSOL-221-F-JB-1168, " Periodic Inspection of Shipping Container LLD-1", provides for a 14-point visual inspection of the general condition of the package, including welds and closure devices, on a 2-year periodic basis.
DPSOL-221-F-JB-1148, " Caging Product in Shipping Container LLD-1", provides a checklist for inspecting and loading of the LLD-1 for each shipment.
It stipulates replacement of the elcstomer 0-ring for the 2R vessel and the gas filled cetal 0-ring for the outer container at each use.
DPSOL 221-F-JB-1167, " Pressure Testing Shipping Container Thimbles", provides for a gas bubble test (15 psig) of the 2R container prior to first use and every 2 years thereaf ter.
The DPSOL-1167 procedure will be revised to require the He mass spect-rometer leakage tests outlined in Parts A and B of Section VI of this report.
DPSOL-1148 will be revised to refer to a new DPSOL procedure that will pro-vide instructions to perform the assembly verification Icak tests for the 2R vessel at each use.
Any vessel not passing the above tests will be reworked and retested if appropriate or discarded.
A copy of each of the current LLD-1 DPSOL's is attached in Appendix B.
DPSOL revisions and new procedure needs associated with the improvement of l
90009311 l
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(.,. _..4 43 the LLD-1 package are summarized in Table VI.
Table VI.
Summary of DPSOL Requirements for the LLD-1 Package DPSOL No.
Title Revisions Required 221-F-JB-1168 Periodic Inspection of Shipping None Container LLD-1 221-F-JB-1148 Caging Product in Shipping 1.
Specify measurements that ensure a Container LLD-1 30% 0-ring compression.
2.
Lubricate threads of 2R cap 3.
Coat the 0-ring with silicone grease (e.g. Propocone or equivalent).
4.
Clean 0-ring seating surfaces.
221-F-JB-1167 Pressure-Testing Shipping Revise to specify the quantita-Container Thimbles tive leak test described in Parts A & B of the section entitled "LLD-1 Leakage Test Requirements".
New Procedure Assembly Verification Leak Provide a new procedure specifying Tests of LLD-1 Package assembly verification leak tests of the 2R vessel by the air bubble, vacuum and glycol method.
VII.
Quality Assurance Verification for the 2R Vessel The NRC has requested assurance that the specification for a full penetra-tion weld at the bottom of the 2R vessel has been satisfied.
The 2R container consists of an lib-inch length of 5-inch Schedule 120 pipe with a b-inch-thick carbon steel plate welded at the bottom (Ref:
Drawing SS-2-899 8).
Fabrication specifications require the weld to be radiographically inspected with the interpretation of the weld quality to be based on Paragraph UW-52 of the ASME Code,Section VIII, Division 1.
A summary of the radiographic history of all 2R containers has been completed.
The radiographs were taken and interpreted by Pittsburg Testing Laboratory personnel.
A total of 116 containers have acceptable welds and auditable quality assurance records; 25 containers have no radiography records; 10 containers certified as acceptable can no longer be found in inventory.
Only 2R containers that have acceptable welds and auditable records are used for shipments.
Appendix A.
Calculated Pressures for Normal & Accident Conditions of Transport A maximum internal pressure of 33 psia is developed within the 2R vessel 7
during the accident conditions.
The pressure was calculated from Van der Waals equation of state using the maximum temperature of 6350F measured during the fire testl of the hypothetical accident sequence. The calculation is shown below.
90009312 7
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a
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"A "W
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l
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2 2
P = RT
+
- VZ V-n b V-n b "W
W "a
"A AA WW Where P
= pressure, atms n
= moles of air =.089 g
n
= moles of water = 0.0011 g
V
= free volume of 2R vessel = 2 liters T
= temp. of 2R = 608*K R
= 0.08206 liter-atm/ mole *K
^A
= 1.33 liter 2 -atm/ mole 2 "W
= 5.464 liter 2 -atm/ mole 2 bA => 0.0366 11ter/ mole r
W = 0.03049 liter / mole The evaluation of the pressure assumes that the gases would be distributed in the unoccupied space in the 2R vessel.
These gases would consist of the air that was scaled in the vessel and the water vapor contained in the air.
The polyethylene i
bags used to bag the button cans would melt but not decompose at the accident temperature; therefore, no credit is given for gaseous products of decomposition.
An internal pressure of 20 psia is calculated from Van der Waal's equation for the normal transport conditions.
The calculation is based on 20l*F maximum temperature for the 2R vessel given in Reference 1 and can be compared with the 18.3 psia value given in Reference 1 (page 28).
If the air in the inner container should reach the temperature of the cans (333 F), the maximum pressure would be 24 psic.
This value can *.e compared with the 22 psia value of Reference 1 (page 28).
The slightly higher calculated pressures of this report are due to the conservative assumption of a small moisture coatent in the 2R vessel.
Appendix B.
DPSOL Procedures for the LLD-1 Package The following DPSOL procedures (attached) are in current use for the inspection, maintenance and containment testing of the LLD-1 package.
DPSOL 221-F-JB-ll48 Caging Product in Shipping Container LLD-1 DPSPL 221-F-JB-ll67 Pressure-Testing Shipping Container Thimbles DPSOL 221-F-JB-ll68 Periodic Inspection of Shipping Container LLD-1.
90009313 t
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- REFERENCES 1.
J. E. Evans and A. A. Cates, " Safety Analysis Report-Packages, LLD-1 Package" DPSPU 74-124-2, Rev. l., April 19 76.
2.
Certificates of Compliance for Radioactive >bterials Packages, DPSOP 176-1,
- p. 23, 3.
United States Nuclear Regulatory Commission, Rules and Regulations, Title 10, Chapter 1, Code of Federal Regulacions-Energy, Part 71, Appendix B.
4.
Title 49 Code of Federal Regulations, Part 178.34, 5.
H. K. Clark, "Re-Evaluation of LLD-1 Package", DPST-79-217, January 16, 1979.
6.
L. C. Schwendiman, et al., " Study of Plutonium Oxide Leakage Rates from Ship-ping Containers", BNWL-2260-9, February, 1979.
7.
Himmelblau, D.
M., Basic Principles and Calculations in Chemical Engineering, Prentice-Hall, Inc., Englewood Cliffs, New Jersey, 1974, p 164.
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LLD-1 No. 123 After 30-Foot Drop Test. (Note held Failure Of The Containment Vessel Support Tube At The Botton Corner Attachment.)
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UOT REMOVE SEPARATIONS DEPARTMENT DPSOL 2.'l-F-J a-116a
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Ju-LiUU Meehaincul Line W' m "v
^~~ua" "v-trot S/78
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132,-2 PERIODIC INSPECTION OF SHIPPING CONTAINER LLD-1
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PURPOSE: To periodically inupec t, chipping cent.uine: LLD-1 (cages) in addition to the inupect. ion of container prior lo each chlprnent. The inner Plt contait.cr ( thirribl -) is inspected biannt ully, and the LLD-.1 is normally inspected at. this time. Thic DPSOL will provide for the inupue Lion of LLD-1 und will comply with chapter V of DPupU yh-12h.
lHOTE] This DPSOL pertains to the preparation of material
- t. hut ic chipped in compliance with ERDAM-0509, the Certificate of Cornpliance', and SARP for the LLD-1 container, nn.1 other Federal Regulat. ions.
RFFERENCE DPSOL: 221-F-JB-1167, Preocure Tes t i ng Shipping ConLui ne r '.'h i mb.l".
CAFETY:
1.
When lif ting cages, lift properly, watch for pinch points, ani use e aution to avot<l falls.
2.
Use toe protection.
3 Do not open thimbles when they are pronsurir.ed.
PADIATICM & CONTAMINATION CONTROL:
1.
Comply with DPSOL 200-Fil-1,' Hegulated Zones - 200 Areas.
2.
Iluve llP survey cages and/or thimbleu prior to inspection ur pre qure Lect.
Record LLD-1 and thimble numberu on dat.a cheel 1. Knen etich nee L ion in comple t.cd, initini and dat.c appropriate colwr.n of dulu sheel 1 if all conditionu of the Seelion are untin-f ac t.o ry. If any condition in not nutic ruc tory, c.r.Luct the uupervici.r.
Vori Py wi th cupervisor the number of LL D-1 shipping contair.ers to be inspected.
Supervicor's Verificnticn A. General Condi tion
~
- 1) Det, ermine that all curfuees of primary and cocondar,. cont.ainers are free of damage and other deformations that could interfere with proper functioning or package safety.
Verify that:
..s a) Outer container labeling io legible and c e. plies with dra. ting D.th5765, rev P-C.
b) Birdcage and lid are tnarked with the ctew n'mber.
c) Radiation label ic intact und legible en the side of bird container incide enge, d) There are no upuninga i n linn ke t. 'I n ege r i n u. b in. mpnre.
e) Check that bird is ceeured t.o eage.
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f) Expc.nded meLul bauket 13 nut, de Nrme1 m re ;, bun 1/2 in, t,utcide the plane of each side.
g) Paint on packaging is in good condition with no large rust spotc.
h) Refractory fiber insulat. ion bcLweru thint:e and bird in in pince and ic in good condition.
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B. Welds
- 1) Visually inspect all welda and have Maintenanet; farfern a dye-penetrant test en any welda showing ubnormalities.
C. Closure Devices
- 1). Inspect all bolts, sealing surfaces, and birdcage closure elements for da= age. Verify that:
a) Birdcage lid is smooth and clean and has teer. machined to allow a gas-filled stainless steel 0-ring to be installed witneu denting the ring, b) Gas-filled 0-ring is not deformed and has no dents or scratches..
D. Leak Test on Inner Container (Thimble)
- 1) Verify that silicone elastomer "salastic" O-ring is intact with no cracks.
- 2) Verify that sealing surfaces of thimble and cap are smooth and unmarred.
t
- 3) Check pressure-test due date on thinble and if due within 3 months, pressure-test per DPSOL 221-F-JB-1167 b) Record thimble leak-test expiration date on thidble and on data sheet 1.
E. Records
- 1) Return completed copy of this DPSOL, including du,a sheet 1, to Shipping and Receiving supervisor.
- 2) A copy o f the periodic inspection data sheet ( da.2 sheat 1) is to be sent to PRD-QA Shipping Container File by the Shipping and Receiving supervisor.
Ocmpleted by Date
__ Time USA DOE SR AIKEN, S. C.
RADI0 ACTIVE FISSILE N.0.S.
TYPE B GROSS WT.
131 LBS.
(59.4 Kg)
MODEL LLD-1 SERIAL N0.
1/2-in. lettering D
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