ML20195F373
| ML20195F373 | |
| Person / Time | |
|---|---|
| Site: | 07106553 |
| Issue date: | 06/07/1999 |
| From: | Adkins J UNITED STATES ENRICHMENT CORP. (USEC) |
| To: | Paperiello C NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20195F379 | List: |
| References | |
| GDP-99-0100, GDP-99-100, NUDOCS 9906140317 | |
| Download: ML20195F373 (11) | |
Text
'71% 663 4
USEC l
A Glotsal Energy Company June 7,1999 GDP 99-0100 l
Dr. Carl J. Paperiello Director, Office of Nuclear Material Safety and Safeguards Attention: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Paducah Gaseous Diffusion Plant (PGDP)
Docket Nos. 71-6553 Response to NRC Request for Additional Information - Renewal of the Certificate of Compliance No. 6553 for Model No. Paducah Tiger Package
Dear Dr. Paperiello:
United States Enrichment Corporation (USEC) letters GDP 98-0228 and GDP 98-0285 dated October 26,1998, and December 21, 1998, respectively, submitted a request for renewal of Certificate of ComplianceNo. 6553 for the Model No. Paducah Tiger Package, including a revised l
Safety Analysis Report (SAR). On April 12,1999, the U.S. Nuclear Regulatory Commission submitted to USEC a request for additional information regarding this renewal request. USEC's response to the NRC's request for additional information is provided in Enclosure 1. The redline / mark-up version of the revised Paducah Tiger SAR pages is provided in Enclosure 2. is a final copy of the Paducah Tiger SAR changes with the insertion and removal instructions.
1 If you have any questions regarding this submittal, please contact Beth Darrough at (301) 564-3422 or Russ Wells at (301) 564-3245. There are no new commitments contained in this submittal.
Sincerely, n
- 5. A.
'lj James N. Adkins, Jr.
/
Vice President, Production Enclosures (as stated) 101 cc:
Mr. Cass R. Chappell, NRC IIQ
,h NRC Region III Office t)~9 NRC Resident inspector - PGDP
'2 " '
NRC Resident Inspector - PORTS 6903 Rockledge Drive, Bethesda, MD 20817-1818 Telephone 301564-3200 Fax 301-564-3201 http://www.usec.com 9906140317 99060f ~~~
-' ' 'ucah, KY Portsmouth, OH Washington, DC PDR ADOCK 07106553 C
PDR,
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GDP 99-0100 Page 1 of 2
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NRC Comment Table 2.5-1 lists calculated stress values for lifting devices based on a package weight of 38,000 pounds. Revise the table to list calculated stress values based on the revised package weight of 40,000 pounds.
USEC Response The package is lifted only when it is empty; the lower half of the overpack is attached to the floor or bed of the conveyance before the cylinder is loaded into it. SAR Section 2.5.1, first paragraph, first sentence states:"The Paducah Tiger overpack can only be lifted when it is empty." In addition, a statement is being added to SAR Section 7,1 (page 7.1-1) to state:"The overpack is only attached l
and detached from the conveyance when empty."
The supporting calculations for Table 2.5-1 have been revised based upon a package weight of 14,500 pounds, to bound the maximum empty weight of 14,470 pounds. Table 2.5-1 has been updated to reflect the revised calculations.
NRC Comment The following documentswere in the previous version of the Safety Analysis Report and should be included as part of the consolidated application:
I
- 1. The fire test report from the reference document," Engineering Evaluation and Test Report of Paducah Tiger for Shipment of Enriched UF (10-Ton Cylinders)".
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- 2. Specification number JSP-526, Revision 8, for the foam used in the package.
USEC Resoonse The fire test report has been included as Appendix A to SAR Chapter 3. SAR Section 3.5.1.2 (page 3.5-1) has been revised to include a reference to Appendix A.
Paducah Tiger overpacks were purchased to nine different revisions of JSP-526, which contained varying foam specifications. Inclusion of JSP-526, Revision 8 in the SAR would not bound the foam specificationsused in all the overpacks. SAR Tables 2.3-2 and 2.3-3 have been compiled from the foam specifications used in all nine revisions of JSP-526 to bound the foam types used in the overpacks t.nd contain all the foam specifications which are safety significant. Two criteria (water absorption and fire resistance) have been added to Table 2.3-2 and one (shear cone angle) to Table 2.3-3 for completeness.
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GDP 99-0100 Page 2 of 2 NRC Comment Revise the application to confirm that the cylinder valve is properly closed prior to shipment.
l USEC Response Proper closure of the cylinder valve is performed during process handling as part of preparation of the cylinder for shipment. The cylinder valve is leak tested prior to disconnection from the manifold used to fill the cylinder or prior to disconnection from the manifold used to remove contaminant gases from the cylinder. These leak ratings ensure that the cylinder valve is properly closed. In those instances where the cylinder valve will not properly close, the cylinder valve is changed and the cylinder valve and cylinder are leak tested to ensure that the replacement valve (including the valve seat and valve-to-cylinder threads) is leak tight.
SAR Section ?.4.3 (page 2.4-1) has been revised to state that the cylinder valve is leakrated as part of preparing the cylinder for shipment.
t l
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. to GDP 99-0100 Redline / Strike-out Changes to KY-665,
" Safety Analysis Report on the "Paducah Tiger" Protective Overpack for 10-Ton Cylinders of Uranium Hexafluoride" Revision 1 i
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1 -
L' Paducah Tiger SAR l
Docket No. 71-6553 Revision 1 l
l 1
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3.5.1.1 Analytical Mod el................................................................... 3. 5 - 1 3.5.1.2 Test M o d e l.............................................................................. 3 3.5.2 Package Conditions and Environment...........
....... 3.5-2 l-3.5.3 Package Temperatures.......................................................................... 3.5-2 3.5.4 Maxim um Internal Pressures..................................................................... 3.5-3 3.5.5 Maximum Thermal Stresses..................................................................... 3.5-3 3.5.6 Evaluation of Package Performance for Hypothetical Accident Thermal Co n d i t i o ns............................................................................................
l 3.6 References............................................................................................................3.6-1 3.7 Appendix A.
. 3.7-1 l
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4.0 C O NTA I N M E NT............................................................................................. 4 - 1 4.1 Containment B oundary............................................................................... 4.1 - l i
4.1.1 Co ntai nment Ves sel............................................................................ 4.1 - 1 4.1.2 Containment Penetrations........................................................................ 4.1 - 1 4.1.3 S eal s and We l d s................................................................................ 4.1 - 1 4.1.4 Closure................................................................................................4.1-2 l
l 4.2 Requirements for Normal Conditions of Transport................................................ 4.2-1 l
4.2.1 Containment of Radioactive Material................................-....................... 4.2-1 4.2.2 Pressurization of Containment Vessel...................................................... 4.2-2 4.2.3 Containment Criterion.......................................
...........................4.2-2 j.
4.3 Containment Requirements for Hypothetical Accident Conditions....................... 4.3-1 4.3.1 Fissio n Gas Prod ucts.................................................................................... 4.3 - 1 4.3.2 Containment of Radioactive Material.............................................. 4.3-1 4.3.3 Co ntainment C ri terio n................................................................................ 4.3 - 1 l
l 4.4 S pec ial Requirements.............................................................................................. 4.4-1 1
4.5 R e fere n c e s................................................................................... 4.5-1 l
5.0 -
S H I E L DI NG E VA L U ATI O N............................................................................ 5 - 1 iv I
1 Paducah Tiger SAR Docket No. 71-6553 Revision 1 Table 2.3-2 Mechanical Properties of LAST-A-FOAM Relative to Density l
Mechanical Property Low-density Foam" liigh-density Foam' Density Range 5.4 - 8.8 lb/ft' 16.2 - 20.16 lb/ft 3
3 3
Nominal Density' 6 - 8 lb/ft 18 lb/ft Physical Property Test Data' Compressive Strength at 75 F 120 - 180 psi 700 - 1200 psi Compressive Modulus at 75 3,716 - 7,888 psi 20,205 - 30,299 psi Tensile Strength at 75 F 110 psi 650 psi Tensile Modulus at 75 F 6,767 - 12,050 psi 24,786 - 32,095 psi Shear Strength at 75 F 55 psi 250 psi Shear Modulus at 75 F 1,461 - 2,923 psi 7,113 - 10,672 psi Flexural Strength at 75 F 138 - 310 psi 858 - 1,235 psi Flexural Modulus at 75 3,192 - 7,719 psi 23,272 - 32,718 psi d
Water Absorption
$; 6% by volume N/A i
Fire Resistance Self-extinuuishine 4
Coefficient of Thermal (3.5 - 5.0x10 in./in./ F over temperature range of-310 F to Expansion
+200 F) a) For the 74 total packages in service,29 have low-density foam with a nominal value of l
6 lb/ ft), and 45 have a value of 8 lb/ft'.
k b) Properties shown are nominal ultimate values in the strongest direction only.
c) Data obtained from the manufacturer, General Plastics Manufacturing Company of Tacoma, Washington.
d) Per ASTM D-2127 or D-2842.
l 2.3-3 I
Paducah Tiger SAR Docket No. 71-6553 Revision 1 Table 2.3-3 Dynamic Properties of LAST-A-FOAM Dynamic Property Low-density Foam Iligh-density Foam Maximum Dynamic 400 psi at 70%
1,855 psi at 65%
Compressive Strength' compression compression impact Energy' 14.3 ft-lb/in' 72.8 ft-lb/in' Absorbed Energy' 13.4 ft-lb/in' 69.1 ft-lb/in' 6
Shear Cone Anale 2 30 N/A a) Data obtained from the manufacturer, General Plastics Manufacturing Company of Tacoma, Washington.
b) Denned as the anale between the axis of the compression niston and the tension cracks when the foam is compressed by a cylindrical piston.
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l 2.3-4
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Paducah Tiger SAR Docket No. 71-6553 Revision 1 1
2.4 General Standards for All Packaces i
The general standards for all packages include an evaluation of the following: (1) minimum package size; (2) tamper-proof features; (3) the method used for positive closure; and (4) the chemical and galvanic reactions between the material of construction and the intended package contents. The Paducah Tiger shipping package meets the general standards for all packages in accordance with 10 CFR 71.43 as detailed below.
2.4.1 Minimum Packace Size The smallest dimension of the container as specified in 10 CFR 71.43(a) must be greater than 4 inches (10 cm). The smallest dimension of the Paducah Tiger overpack is 72 inches; therefore, this requirement is met.
2.4.2 Tamper-proof Feature l
Tamper-indicating devices (TIDs) are required as evidence that the package has not been opened by unauthorized personnel. A matching pair of welded rings is provided on the lid and body of the overpack for attachment of TIDs. The TIDs are numbered seals. These numbers are verified on receipt. The presence of these seals demonstrate that unauthorized entry into the package has not occurred.
2.4.3 Positive Closure A closure system that cannot be opened unintentionally is required. The containment vessel (48X cylinder) is completely enclosed by tae overpack. Proper closure of the containment boundary (i.e. closure of the cylinder valve) is verified by leakratina the cylinder valve after filline and/or nrenarine the cylinder for shipment. The overpack is equipped with a positive closure system that includes four ratchet turnbuckles and eight guide / ball lock pins connecting and restraining the opening of the overpack lid and body.
2.4.4 Chemical and Galvanic Reactions The materials used to construct the Paducah Tiger overpack will not caase chemical, galvanic, or other reactions in the overpack or between the overpack and its contents. The shipping package 2.4-1
Paducah Tigcr SAR Docket No. 71-6553 Revision 1 Table 2.5-1 Response of Lifting Devices to Requirements of 10 CFR 71.45(a)
)
l Item Calculated Stress' Allowable Stress Design Margin (psi)
(psi) j 2.170 nsi 16.200 nsi 6.47 Luc Tension thru Eye 4220 14,400 2.41 f
Luc Shear thru Eve 3.520 38.700 9.99 Luc Bearine from Pin 8.360 21.600 1.53 Stiffener Comnression 10.610 21.600 1.04 Stiffener Tension 10.350 18.000 0.74 Luc Weld to Too Bracket Plate 14.900 18,000 0.21 Ton Plate Weld to Stiffener 6.850 18.000 1.63 Top Bracket Plate to Base Plate 14.500 21.600 0.49 Base Plate Bendine 5.900 gog l {lrackelyfeld to Skin Plate 4.160 12.000 1.89 Skin Plate Shear 4.350 18.000 3.14 Skin Plate Tension 123 150 0.22 Foam Bond Stress 414 21.600 51.2 TS4x4 Tube Bendine 1.650 14.400 1 76 Ton Plate (Ratchet) 2.780 14.400 4g Bottom Plate (Ratchet) 1.220 12.730 9.42 Weld of Rachet plates 18.2 Bottom Luc Bearina 3.180 58.000 a) Calculated stress values were based on a nackace weicht of 14.500 pounds.
2.5-3 1
Paducah Tiger SAR Docket No. 71-6553 Revision 1 3.5 Hvoothetical Accident Thermal Evaluation The Hypothetical Accident Condition (HAC) specifies that the container be subjected to a 30-minute fire at a temperature of 1475 F (800 C) using a flame emissivity of 0.9. A surface absorptivity coefficient of no less than 0.8 must be used for the container surfaces. After the fire, the container is allowed to cool by radiation and convection to the ambient conditions at a temperature of100 F.
3.5.1 Thermal Model 3.5.1.1 Analytical Model No analytical model was developed and analyzed to evaluate the thermal performance of the Paducah Tiger overpack for hypothetical accident events.
3.5.1.2 Test Model A damaged package, consisting of a prototype Paducah Tiger overpack and a 48X cylinder filled with more than 20,000 pounds of steel shot and BaSO, to cimulate an actual fully loaded cylinder, was subjected to a 1475 F fire test conducted by Protective Packaging, Inc., of Tacoma, Washington in November 1971.[9] This test is included as Anoendix A. Before undergoing the j
fire test, this single test package was subjected to two different series of drop tests. Each series of drop tests involved a 30-foot free drop test followed by a 40-inch pin puncture test. In addition, each series of drop tests was performed on opposite edges of the overpack, one on the lid and the other on the body. [10] Therefore, the prototype incurred twice as much physical damage as required by the 10 CFR 71.73 hypothetical accident conditions.
The second series of drop tests, where mild carbon steel breakaway plates were used on the bottom of the overpack body, caused the greatest damage to the package. The 6-inch diameter i
bar penetrated the outer skin, breakaway plates, foam, and 3/16-inch carbon steel inner liner of the overpack, thus exposing the foam insulation and the 48X cylinder to the extemal environment. Due to design changes since the development of the prototype which was actually tested, this level of damage would not occur to a production overpack. The carbon steel
. breakaway plates which were punctured on the prototype were not used in the production 3.5-1
Paducah Tiger SAR Docket No. 71-6553 Revision 1 7.1 Loadine the Paducah Ticer The Paducah Tiger is intended for the shipment of a 48X 10-ton cylinder. The cylinder may be full or contain a heel. Cylinders containing UF must be inspected in accordance with ANSI 6
N14.1. Cylinders which are empty (i.e., net weight less than 50 pounds) need not be handled in -
accordance with this procedure.
Prior to loading the cylinder into the overpack, the lower half (body) of the overpack must be secured to the floor or bed of the conveyance. The conveyance may be a dedicated rail car or a truck trailer. The overnack is only attached and detached from the conveyance when emnty.
7.1.1 Insnection of the Overnack and 48X Cylinder Inspection of the overpack and the 48X cylinder is required to verify that aoth are acceptable for use. Defects identified in the inspection must be corrected before use.
1.
Inspect the overpack in accordance with Table 8.2-1, 2.
Inspect the 48X cylinder in accordance with the requirements of ANSI N14.1.
3Property "ANSI code" (as page type) with input value "ANSI N14.1.</br></br>3" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..
Visually inspect the cylinder lifting lugs prior to attachment of the lifting slings.
4.
Perform a surface contamination survey and a radiation survey, and record the survey results.
7.1.2 Loadinn the Overnack Loading of the overpack requires a suitable lifting device. The body of the overpack must be secured to the bed or floor of the conveyance prior to loading the cylinder into the overpack.
Prior to loading the 48X cylinder into the overpack, verify that the UF weight is either less than 6
350 pounds, or between 12,000 and 21,030 pounds; and that the pressure within the cylinder is less than 0 psig.
1.
Using a suitable lifting device, place the cylinder into the overpack body with the valve end of the cylinder facing the lid guide in the body.
CAUTION: The opposite (nonvalve) end of the cylinder is tapered. The tapered end of the cylinder must rest in the matching tapered shape of the body of the overpack. The body of the overpack may be damaged if the cylinder is not correctly oriented.
7.1-1