ML20042G888
| ML20042G888 | |
| Person / Time | |
|---|---|
| Site: | 07109790 |
| Issue date: | 05/15/1990 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20042G886 | List: |
| References | |
| NUDOCS 9005160231 | |
| Download: ML20042G888 (3) | |
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NUCLEAR REGULATORY COMMISSION g
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SAFETYEIIALUATIO'NREPORT-
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Model No. A1W-3 Holddown/ Support Barrel and Shroud-Disposal Container-Certificate of Compliance No. 9790 Revision No. O' i
By application. dated March 31, 1983.as: supplemented-the Division of Naval Reactors,U.S.Departmentof: Energy _requestedacertIficateofCompliancefor
'the A1W-3 Holddown/ Support Barrel and Shroud Disposal Container-(HD/SB & SDC).
PACKAGE DESCRIPTION-The A1W-3 HD/SB & SDC is a closed HY-80 steel cylindrical container consisting of an 8.00 inch thick bottom plate (at its centerline), an 8.00 inch thick! top-cover:(at its centerline) and a cylinder of four inth wall. thickness. Pads are 1!
-provided on the.inside wall of the cylinder and on the inside: surface of the-1
-bottom plate to aid the. positioning.the container' contents.' Four thin-walled rectangular support posts which are welded to the bottom plate. pads maintian the
-l holddown barrel assembly'at a height of'approximately 33' inches.above the bottom, plate. The outside diameter of theJcylinderJis 105. inches, the. top cover dia-j meter is 112.50 inches, and the diameter of the bottom plate is 121 inches.
Additional shielding is provided at the lower portion of the.-cylinder by a-28 inch high by 3.5Linch thick annular shield plate.. The overall height-of the:
-container, including the lifting lugs, mounted on its railcar pad is 137.12:..
inches above the.railcar-deck. Total weight of the: package is 160,000 pounds.
STRUCTURAL EVALUATION 4
The' demonstration of' compliance with 10 CFR 571.45 (Lifting and Tie-down-
. 1 Standards' for All Packages) was done by-analysis. The results of'the analyses i
indicated that all calculated stresses were less than the yield-strength of the meterial. By comparison of the various load carrying capacities of the related components, the applicant concluded that the ability _ of the container to meet i
the other requirements of 10 CFR Part 71 would not be impaired.under excessive load.
Standard textbook equations and DUZ-02 computer program werelused to evaluate the container for normal conditions.of transport.. Because-of ~ the weight and the size of the container, as well as its shipping configuration,'only the bottom plate was evaluated for the effects of a 1-foot free drop test. - The package was also evaluated for damage produced from a 150-pound, 6-inch diameter.bar having the energy equivalent of;a 15-foot drop,' applied to all surfaces' oth.er' than the mounting _ surface. The results of the analyses and the brittle fracture assess-ment adequately demonstrated that the container would remain intact and perform-its intended safety function under normal conditions of transport.
The container was evaluated for a 30-foot free drop test against the top, top and bottom corners, side, and-bottom surfaces. The impact force and the de-celeration (G-load) were determined by the energy. balancing method. Standard textbook equations and DUZ-02 computer program were used to calculate the 9005160231 900515 9$
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. stresses. The results indicated that the. containment boundary woulde not fail',
but the container ~would be subjected to local deformations.
In most cases,_
only. elastic deformation of the contents would result from various drops.
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-However, for flat bottom and bottom corner drops, the following deformation-would occur: support barrel.- 1.03 inches, holddown barrel supports --1.48 inches, and shroud canister base:- 1.24 inches.
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4 The.40-inch puncture' test and the thermal-test were also evaluated by analysis, l
i The container was analyzed for puncture on its side and end surfaces. The f
results' indicated that the 6-inch. diameter bar.would not penetrate the con-tainer. The_ application conservatively assumed'that the puncture bar would--
penetrate the'3.5-inch shield plate and 0.95-inch of the cylinder wall. This.
4.45-inch total penetration was used in the shielding analysis; :No?signi-
.ficant ther.nal stress would be developed due to differential thermal expan-
- sions'of the various' components because of: clearance between the' contents and
.the ~ container. :
THERMAL EVALUATION.
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Normal Conditions.
TheA1W-3Holddown/SupportBarrel(HD/SB)andSh'roudDisposalContainer(SDC) was evaluated for the. normal. heat condition of: transport assuming an ambient.
temperature of 130'F and a negligible" internal heat source. The maximum tem-1 perature calculated to occur anywhere within the package was approximately 181'F. For an ambient temperature of'100*F, the maximum package temperature would be about 155'F. The minimum temperature assumed for the cold condition of transport was -40*F.
In this temperature range, -40' to 181'F, there were a
no significant problems with either material-properties or thermal stresses.
Accident Conditions
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The applicant evaluated the HD/SB.and'SDC for accident = conditions assuming.a maximum of 14 gallons of residual water.
The maximum' temperature calculated within the containment vessel was approximately 775'F. The maximum package-
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surface temperature' was about 920'F. None of:the package components will melt i
or be damaged at these temperatures. There are no gaskets. or 0-ring seals as the containment vessel and all penetrations are welded shu~t.. The maximum pressure within the package was calculated assuming the' volumetric expansion of heated air and' steam pressure resulting from the 14 gallons of. residual 1
water. Themaxigumpressurebasedonatemperatureof777'Fandapackage
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volume of.240 ft is approximately 395 psia or'380 psig.
CONTAINMENT EVALUATION-i L
The containment boundary for the A1W-3 Holddown/ Support Barrel-and Shroud Disposal Container is. comprised of the package body,: top cover and bottom plate. The top cover and bottom plate are welded to the package body with full penetration welds. The vent lines in the top cover and'the drain ~ lines in the bottom plate are plugged and welded prior to shipment. There are no other penetrations in the containment boundary.
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. The package contents consist of irradiated metallic hardware. DThe only.
potential sources for radioactive' release are-crud and activated corrosion products. Based on the' limited quantity of potentially releasable material,.
a and the fact that the package is welded shut.. staff has concluded that the-package meets.the containment requirements'specified in 10 CFR 671.51' for.
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' both normal and accident conditions ofstransport.
SHIELDING EVALUATION' The applicant ~ demonstrated by analysis withi the SPAN-4L shielding 3D computer.
j program:that the shipment of the proposed contents in the A1W-3 HD/SB&SDCL container was in compliance.with the radiological limits'of 10 CFR 71. The staff ? reviewed:the applicant's shielding analysis and found. it-to be acceptable ~.
The applicant's" accident analysisLshows a' maximum dose rate of 570 mrem /hr at.
3:teet from the side of the container. This is within the-limits of.
, n 10 CFR 571'.51.
CRITICALITY No' criticality evaluation is required. The package contains onlyfirradiated
. hardwares.
OPERATING PROCEDURES Description of~the procedures for loading'the A1W-3 HD/SB.and SDC are-provided in Chapter 7 of the application..The container will be buried at a disposal-
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. facility. Thus, there is no procedure for: unloading the container.
.p ACCEPTANCE TESTS AND MAINTENANCE PROGRAM I
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Chapter.8 of-the application specifies the acceptance. tests to be performed.-
These. tests include visual inspection and either liquid: penetrant or. magnetic particle test.of-all welds. The lifting lugs and-the dhroud. canister are load tested to 150% of design loads without yielding. A maintenance program is not required because'the container will be used for..only~a single shipment.
CONCLUSIONS K
Based upon the information in the application, the staff concludes that the l
package design meets the requirements of 10 CFR Part 71.
e, h
y Charles E. MacDonald, Chief.
s Transportation Branch o
- Division of,Saf6 guards g
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and Transportation, NMSS Date:
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