ML20003H393
| ML20003H393 | |
| Person / Time | |
|---|---|
| Site: | 07109144 |
| Issue date: | 04/27/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20003H383 | List: |
| References | |
| NUDOCS 8105050748 | |
| Download: ML20003H393 (6) | |
Text
.
O
- u. S. Nucleer Re9uietors Commissioa
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Division of Fuel Cycle and Material Safety Safety Evaluation by the Transportation Certification Branch CHEM-NUCLEAR SYSTEMS, INC., MODEL NO. SGC-1 PACKAGING Docket No. 71-9144
SUMMARY
By application dated January 19, 1981, as amended, Chem-Nuclear Systems, Inc.
requested approval to deliver a steam generator lower assembly to a carrier for transport in the Model No. SGC-1 package. Based on the statements and representations as contained in the application, as amended, we have concluded that the contents and packaging meet the requirements of 10 CFR Part 71 subject to the conditions and exemptions stated below.
SUBMITTALS 1.
Chem-Nuclear application dated January 19, 1981.
2.
Supplement dated March 31, 1981.
3.
Suoplement dated April 21, 1981.
DRAWINGS The packaging is constructed in accordance with Chem-Nuclear Systems, Inc.
Drawing Nos. Il0-2700-E01, Revision A; 110-2700-E02, Sheet Nos. I thru 3 Revision A; 110-2700-E03, Revision A; 112-2700-E01, Revision A; and 115-0127-001, Revision A.
PACKAGING DESCRIPTION A steel shipping container for shipment of the lower assembly of a steam generator. The external dimensions of the packaging are 42'6" length and ranging in diameter from 13'5" to 15'7".
The packaging consists of a cylindrical section rolled from 2.5" thick steel plate with 2.75" thick end plates. The packaging is flanged down the center line of the cylinder and sealed with a Neo;-ene gasket and 112, two-inch bolts on 12-inch centers. The lower shell assembly has two external saddle base support assemblies. The packaging is provided with two drain plugs. The packaging weight is 276,000 pounds and the gross weight is 722,000 pounds.
The top and bottom openings are sealed with 3 to 5-inch thick steel plate ~
welded to the steam generator. All other openings are sealed with 2" thick (minimum) plate or bar steel and welded closed.
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PACKAGE CONTENTS (1) Type and form of material Steam generator lower assembly containing radioactive material adhering to the inside of the tube surfaces.
(B) Maximum quantity of material per package 750 Ci of principally corrosion products, mainly Co-60.
CONTAINMENT Primary containment is provided by the 2.5" to 2.75" thick steel packaging which is in two halfs and sealed with a Neoprene gasket and 112, two-inch bol ts. Two drain plugs on the outer packaging are sealed. Secondary con-tainment is provided by welding steel plate (3" to 5") thick to all openings on the steam generator and decontaminating the exterior surface of the assembly to no more than 220 dpm/100 cm2 STRUCTURAL The applicant has performed various structural analyses and engineering evaluations to demonstrate the package has adequate structural integrity to meet the requirements of 10 CFR Part 71 with administrative controls in lieu of certain requirements. The staff agrees with the applicant's conclusion that the package has adequate structural integrity and administrative controls to provide an equivalent amount of safety to the requirements of 10 CFR Part 71 subject to the conditions listed below.
A.
General Standards for all Packaging Chemical and Galvanic Reaction There is no significant chemical, galvanic, or other reaction among the packaging components, or between the packaging components and the package controls.
Positive Closure Inadvertent opening of the package is prevented by means of positive closure devices.
Lifting Devices (1)
Four lifting lugs are shown by analysis to be capable of lifting three times the maximum package weight without exceeding material yield stress in any material of the packaging.
. (2)
It is also shown by analysis that the lid lifting devices are capable of supporting three times the weight of lid and any attachments without generating stress in any material of the lid in excess of its yield strength.
(3) The requirements of covering the lid lifting devices are met by imposing a licen*ing condition in the certificate.
(4) The staff agrees with the applicant's conclusion that failure of lifting devices under excessive loads would not result in any loss of packaging effectiveness or release of radioactive ma terials.
Tie-Down Devices Applicant has shown by analysis that the tie-down devices which are structural parts of the package are adequately designed to meet:
Trailer tie-down system:
Barge tie-down system:
longitudinal 1.5 's longitudinal 1.5g's 9
lateral 1.5g's lateral 1.5g's vertical 75 tons vertical 1.5g's i
These values have been justified on the basis of limiting the land speed to 10 mph and 5 mph on grades and curves and analyzing the barge transport in accordance with Draft ANSI N-14, N552 (October 1976), " Proposed Guide for Water Transportation of Irradfated Nuclear Fuel."
B.
Structural Standards for Type B and large Ouantity Packaging Load Resistance The package is shown by analysis to be capable of withstanding statically five times of its fully loaded weight uniformly distributed along its length without generating stress in any material of the packaging in excess of its yield s+,rength.
External Pressure Applicant has shown by analysis that the packaging design meets the regulatory requirements.
C.
Normal Conditions of Transcort Heat 0
The maximum package temperature has been estimated to be 149 F.
The effects of this temperature increase from the rcom temperature on material properties are insignificant and on stresses are not expected to cause the stresses to exceed material yield stress.
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. Cold 1
The stresses caused by thermal contraction under the cold (-400F) environment are judged not to reduce packaging effectiveness sub-stantially. All materials meet the standard Charpy V-notch test with a minimum of 15 ft-lbs impact energy at -400F.
Pressure The cask containment vessels have been shown to withstand atmospheric pressure considerably greater than 0.5 times standard atmospheric pressure.
Vibration The vibration loading is judged not to have significant effects on packaging safety.
Water Soray Water spray will have no effect on the package.
Free Droo The package was analyzed for a one-foot bottom free drop on the forward saddle. The STARDYNE finite element structural program showed that other than localized yielding, no permanent distortions occurred which could comprise the integrity of the package and its closure. Other orientations were not examined since a package of this size and weight could not be dropped one-foot in norraai conditions of transport except on ;ts bottom.
Corner Drop Not applicable for this design case.
Penetration The staff agrees with the applicant's judgement that this regulatory loading has insignificant adverse effects on the package design.
Compression Not applicable to the present design case.
D.
Hypothetical Accident Conditions The applicant has requested an exemption from 10 CFR 571.36, Hypothetical Accident Conditions, for this package. The basis for the exemption request
- is the inside surfaces of the steam generator tubes are contaminated by a gnacious magnetite film of deposited radioactive products, mainly Co It is estimated that the steam generator will contain no more than 750 Ci of deposited gamma activity deposited over approximately 4.5 x 107 2 in a non-readily dispersible form (about 20u Ci/cm ),
2 cm As an administrative control, the land speed will be limited to 10 mph (5 mph on grades and curves) and the land shipment phase would be escorted by a person equipped and knowledgeable in the use of a radiation survey instrument. The escort would be provided with written procedures to be followed in an emergency situation and will be provided with supplies to permit the establishment of a radiation exclusion area in the unlikely event any shielding was lost due to an accident.
Considering the nature of the material being transported, the speed controls and knowledgeable escort the NRC staff is in agreement that the shipment provides an equivalent amount of safety to that provided for in the regulations (Part 71).
SHIELDING (Normal Conditions of Transport)
The ability of the packaging to meet the shielding requirements of 49 CFR 5173.3931 or j will be demonstrated prior to each shipment by taking actual radiation measurements.
CONDITIGNS The safety of the cask was confirmed by the Transportation Certification Branch on the basis of the following conditions and exemptions:
(A) The steam generator lower assembly must be sealed in accordance with Figures 1,2-3, Rev. 2 and 1.2-5, Rev.1 (pp 1-10 and 1-11). The exterior surface of the steam generator lower assembly must be decon-taminated to no more than 220 dpm/100cm2, (B)
In lieu of meeting the requirements of 10 CFR ll71.31(d), tiedowns, and 71.36 and Free Drop, Appendix A,10 CFR 71:
(i) An escort must be provided during land transport which is l
knowledgeable in the use of radiation survey instrument, be i
equipped with an appropriate survey instrument, supplies to l
permit the establishment of a radiation exclusion area, and be provided with written procedures to be followed in an emergency situation.
(ii) Appropriate means must be taken to control the maximum land speed to 10 mph. On curves and grades, the maximum land I
speed must be limited to 5 mph.
l
(C) The lifting devices must be securely covered during' transport to prevent their use during transport as a tie-down device or for lifting the loaded package.
(0) The packages authorized by this certificate must be transported on a vehicle, inland water craft, or barge assigned for sole use of the licensee.
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Charles E. MacDonald, Chief
-Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date:
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