ML20203J673
| ML20203J673 | |
| Person / Time | |
|---|---|
| Site: | 07105942 |
| Issue date: | 07/01/1986 |
| From: | Cunningham G GENERAL ELECTRIC CO. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20203J676 | List: |
| References | |
| 27196, NUDOCS 8608050365 | |
| Download: ML20203J673 (13) | |
Text
RETURN TO 396-SS 7469MB GENERAL $ ELECTRIC i
NUCLEAR ENERGY BUSINESS OPERATIONS GENERAL SECTRIC COMPANY e VALLECTOS NUCLEAR CENTER
- PLEASANTON, CAUFORNIA 94566 July 1, 1986
e 4
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RECEIVED g.
t Mr. C. E. MacDonald, Chief
- 2 JUL 151986 I Transportation Certification Branch Offico of Nuclear Material Safety and Safeguards 9
COMMISSION U.S. Nuclear Regulatory Commission NMSS r'
Washington, D.C. 20555 C9
"", O y's A Ref.:
- 1) Certificate of Compliance No. 5942
- 2) Application for Amendment, Feb. 28, 1986
- 3) Supplement, May 8, 1986
- 4) Letter, C. E. MacDonald to C. E. Cunningham, 5/20/86
Dear Mr. MacDonald:
This letter is in response to your letter of May 20, 1986.
Enclosed are copies of General Electric Drawing No. 183C8253. This drawing was developed under Quality Assurance Program QAP-1 (Docket 71-0170) and replaces Drawing No. E 04-045 submitted May 8, 1986 (Ref. 3).
An analysis of the cask divider under the 30-foot drop accident condition is included as Enclosure 2 to this letter. This analysis constitutes Attachment C to our application of February 28, 1985.
Replacement pages for the loading / unloading procedure for the Model 700 cask (Chapter XVIII, Section R) submitted with our May 8, 1986 (Ref. 3) letter are included here as Enclosure 3.
Sincerely,
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L C. E. Cunningffam Sr. Licensing Engineer
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1 ENCLOSURE 1 GE DRAWING No. 183c8253 e
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CASK DIVIDER (FUEL BASKET) MODEL 700 SHIPPING PACKAGE WELD EVALUATION The purpose of this evaluation is to show the welding prescribed for the cask divider is adequate to preclude any massive weld failure due to a postulated 30 foot drop. Details for the cask dividers are given in CE drawing 183C8253.
The impact loading orientation considered in the report is the side-down impact configuration.
It is rationalized that this orientation imposes the greater loading on the weld area at the 3 locations shown in Figure 1.
In the head and bottom on orientations the cask divider welds are not load-up.
Location 1 X
h
?Y 2
1
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Location 2 4
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Location 3 Figure 1.
Cask Divider Cross Section Location 1 - Impact in the x-direction Location 2 - Impact in the y-direction Location 3 - Impact in the x-direction
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2-t In the calculation for weld stress, forces from both the fuel element and the weight of the divider structure are considered.
1 Neutron Products. Inc. (Ref.: Certificate of Compliance No. 5942, Docket
~
71-5942, reference dated February 28, 1986), determined a maximum g-loading of 270 g for the GE Model 700 under the 30-foot drop, side orientation. This g-loading is established by assuming that all of the kinetic energy of the shipping package (cask, contents, and overpack) is absorbed by deformation of 1
the lead shielding of the cask. The deformation and maximum g-loading are l
calculated using a " dynamic flow pressure" and the geometry of the cask. A
]
f conservatively high value of the g-loading is obtained by using a dynamic flow j
pressure of 10,000 psi (ref: ORNL-NSIC-68, A Guide for the Design, Fabrication, and Operation of Shipping Casks for Nuclear Applications, February, 1970).
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On this conservative basis, the energy to be absorbed by lead deformation is i
the weight of the package times the 30-foot distance. Then, the average j
cross-sectional area of lead times the dynamic flow pressure yields the force i
to defc,rm the lead. The depth of lead deformation is obtained by dividing the energy value by this force. The corresponding g loading is determined by dividing the 30 foot distance by the deformation.
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In the analysis, the structure and fuel element are assumed to have the same j
mass and geometric property throughout its length. Therefore, a model j
consisting of a one-inch length segment is all that is needed to be considered in the evaluation.
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The method of analysis applies statically an acceleration of 270 g's to both the l
divider structure and the fuel element. The assumption is made that the fuel element moves simultaneously with the structure.
In kcation 1 configuration, the analytical model consisted of a rigid frame with the welds assumed to have 3
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moment carrying capability (full penetration welds). The mass for the fuel 1
j element is distributed uniformly along the side. This analysis was executed l
using the finite element LIBRA program, i
=.
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Plate material = Stainless Steel Type 300 6 6
'i Thickne n =.25 in.
mats (TYP)
(x-direction oni
)
o to Fuel weight = 4.85 lb/ segment Segment length = 13-5/16 in.
or
= 0364 lb/in 3(I) a en 2( C ois.
-W n# ~x
=
=
270 g's The analysis yields the following forces at Node 1:
271.2 in-lb Moment 117.2 lb.
Axial Force 199.8 lb.
Shear The combined bending and axial stress check is 117.2 ) + I(6)(271.2))
I
.25
(.2512 gi 30000 30000
.016 +
.866
.882 ---> OK where: allowable axial and bending stresses equal to the yield stress.
The specified weld is a full penetration weld with an effective throat equal to the thickness of the welded part. The veld material property being greater in strength than the parent material, makes the welded connection also satis-factory.
At Location 2, the weld is a full penetration continuous weld. The connection is assumed to be a moment carrying connection. The configuration for this weld evaluation is
W
- (.364)(270) = 98.4 lb.
gg W
= (.25)(3.19)(.28)(270) = 60.3 lb.
str j
_s 270 g's E
/c Weld 3.19" The loading in the weld is (08.4)(3.19)
(60.3)(3.19) 55.3 in-lb g
w 8
12 158.7 lb.
94.4 + 60.3 P
r The loadings at Location 2 are less than they are at Location 1 (same weld).
Therefore, the weld is adequate.
In Location 3, the weld is an intermittent fillet with 1/3 cover.
The connection is assumed to be a primed condition. The configuration for this weld evaluation is W
= (270)(.364) = 98.4 lb fuel L
W
= (3.62)(.25)(.28)(270) = 68.4 lb str f,
y 270 g's
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.62" fillet weld
A vertical shear load of 156.8 lb. is required to be taken by the weld. The required weld size is i
t, -
f
.01 in.
A minimum weld size of.01 inch is required at Location 3; however, a' weld size of.125 is used.
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t ENCLOSURE 3 i
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GENERAL ( J ELECTRIC sm w
IRRADIATION PROCESSING OPERATION RADIOACTIVE MATERIALS SERVICES 1
REMOTE HANDLING GPERATIONS STANDARD OPERATING PROCEDURE CHAPTER SHIPPING PACKAGE sEcum Loading / Unloading Procedure for XVIII. ASSEMBLY / DISASSEMBLY R.
GE Model 700 with Extension ee.
Check the drain valve, fill valve, pressure relief valve, the lid gasket area, and the cask gasket area for leakage.
If bubbles are observed, repeat the appropriate preceeding procedures to stop the leak.
If no bubbles are observed, the cask has passed the leak test.
ff.
Monitor dose rate and raise the cask out of the pool. Rinse external cask surfacs with demineralized or potable water.
gg.
Move the cask to the side of the pool, hh.
Attach a vent hose to the cask fill valve.
11.
Open the fill valve and vent the cask pressure to a contaminated ventilation exhaust duct or other approved area.
Close fill valve and remove the vent
- hose, jj. Transfer the cask to the decontamination area.
kk.
Decontaminate the cask in accordance with internal procedures.
Remove all residual water from cask surfaces and crevices.
Perform radiation survey for contamination of external cask surfaces. Although the surface of the cask is not the external surface of the packaging (the jacket is the external surface), it is recommended that the provisions of 10CER71.87(h) be followed 11.
Check that the fill and drain valves are shut.
Apply teflon tape thread sealant or equivalent to the two stainless steel mm.
plugs removed from the fill and drain valves.
Install and tighten the plugs in the fill and drain valves, Apply a " FULL" or " EMPTY" tag to cask as appropriate.
nn.
Apply tamper-proof seal to designated lid bolt.
oo.
pp.
Attach clean properly rated slings to the ears of the cask.
Lift the cask and transfer the cask to the protective jacket base.
qq.
Align the cask in the base so that black alingment marks face each other.
Inspect the protective jacket and full cask for any signs of damage prior to rr.
assembly.
CAUTION: THE ENTIRE ASSEMBLY MUST BE KEPT FREE OF CONTAMINATION.
DATE ISSUED SUPERSEDES ISSUE REVISION NO.
O N
9 msUED BY:
J. I. Tenorio DATED:
New
r cm G EN E R AL (j E LECTRIC 3/86 1RRADIATION PROCESSING OPERATION RADI0 ACTIVE MATERIALS SERVICES
'g REMOTE HANDLING OPERATIONS STANDARD OPERATING PROCEDURE CHAPTER SHIPPING PACKAGE SECTION Loading / Unloading Procedure for XVIII. ASSEMBLY / DISASSEMBLY R.
GE Model 700 with Extension 9.
Preparation for Shipping Attach clean properly rated slings to the shackles on the side of the a.
protective jacket, b.
Carefully position the protective jacket over the cask and base assembly.
Align the jacket with the cask and base assembly and lower the protective jacket into place.
c.
Install all eight jacket bolts.
Insure that all tension is taken off of the crane. Tighten all eight jacket bolts to 100 ft-lb 25 ft-lb.
d.
Lift and transfer the assembled package to the truck-trailer. Observe and inspect tiedown of package to trailer bed.
Perform the final radiation survey of the assembled package including smear e.
check of external jacket surfaces. Radiation levels must meet the requirements of 10CFR71.47 and 71.87.
f.
Complete the shipping papers as required by applicable internal procedures and government regulations.
g.
Remove all old shipping labels. Attach appropriate DOT shipping labels, h.
Attach a security seal to the package in the holes provided in the protective jacket and base plates.
- i. Return shipping package to:
General Electric Company Vallecitos Nuclear Center P.O. Box 460 i
Pleasanton, California 94566 s
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DATE ISSUED SUPERSEDES ISSUE REVISION NO.
O PAGE p)F g
ISSUED BY:
J. I. Tenorio DATED:
New