ML20149G755
| ML20149G755 | |
| Person / Time | |
|---|---|
| Site: | 07104909 |
| Issue date: | 03/30/1987 |
| From: | Nardi A WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20149G758 | List: |
| References | |
| 28016, LA-87-10, NUDOCS 8802180393 | |
| Download: ML20149G755 (16) | |
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LA 87-10 Westinghouse Water Reactor -
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' PittsburghPennsyfvania 15230-0355 Electric Corporation Divisions Ma rcn - 30, 1987 6
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U. S. Nuclear Regulatory Commission
/ p ATTN: Mr. Charles E. MacDonald, Chief fm h?B (\\9N }.
W Transportation Certification Branch g
Division of Fuel Cycle and Material Safety d;
Office of Nuclear Material Safety ano Safeguards p,
Washington, D. C. 20555 g
pd Gentlemen:
4 'f7 p.
Subject:
Amendment to Certificate of Compliance Number 71-4909 The Westinghouse Electric Corporation hereoy submits this application for amenoment to Certificate of Compliance Nunber 71-4909 (Package Identification USA /4909/B()F) to authorize modifications to the existing protective overpaks to increase the length of tne overpaks.
Attachment I to this letter provides a summary description of information provided with this request as Attachment II.
Enclosed is a check in the amount of $150 in payment of the fee specified in 10CFR170.3i for this application for amendment.
If you have any questions concerning this application, please contact me at the above aooress or oy telephone on (412) 374-4652.
Very truly yours,
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Attachment-l Letter Number LA-87 --10 Dated: March 30,.1987 s
This attachment provides-a summary of the documents- 'provided as Attachment II.
1.
Discussion This document provides a general : history of the evo'l'ut ion o f the W-21PF-1 design and documents by reference' the nuclear criticality safety and. structural evaluations.
An overview of the need for :the modi fications described. by this request for a - license..
edment is also provided.
2.
Drawings Five drawings are included in this package which replace -all previously submi t ted drawings.
These revised dra,vings describe both the original overpak design and the modi fications being requested.
Additional corrections were made as necessary to accurately reflect the overpak design.
3.
Attachment Il-A - Procedure for Modifying the W-21PF-1 Protective Overpak to Dimensional Conformance.
This attachment constitutes the specific procedure to be foilowed in modifying the overpaks.
4.
Attachment Il-B - Acceptance Criteria for Phenolic Foam Additions to Modified W-21PF-1 UF. Shipping Container.
This document presents the procedure to ensure that each modi fied overpak will have sufficient foam at the required density.
5.
Attachment Il-C - Justi fication for reduction of-Phenolic Foam by 0.15" along a 2" strip.
This document presents an engineering evaluation to justify the reduced thickness of foam that will be present in the modified-overpacks due to the presence of a 2 inch 4 wide backup strip, behind the weld seams.
6.
Attachment il-D - Typical operating procedures for W-21PF-1 packages and inservice-inspections and maintenance to ensure packaging compliance.
This document presents typical oporating procedures to assure safe handling of UF.
during loading and preparation for shipment.
Quali ty overchecks defined in these procedures assure that each packaging is in compliance with all shipping specifications.
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. Attachment iI-Letter Number LA-87-10 Dated: March-30,;1987 TABLE OF CONTENTS 1.
~ Discussion 2.
Reference Drawings 3.
At tachment Il-A - Procedure fo'r Modi fying the _. W-21PF-1L Protect ive Overpaks-to Dimensional Conformance.
4.
Attachment il-8 ~ Acceptance Cri teria for Phenolic Foam Additions -to Modified W-21PF-1 UF. Shipping Container.
- 5. 1-C - Just i ficat ion for Reduction of Phenolic Foam. by 0.15" Along a 2" Strip.
- 6. 1-D - Typical Operating Procedures for. W-21PF-1 Packages and Inservice inspection and Maintenance to Ensure Package Compliance.
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1.0' Discussion The 21PF-1 outer protective' package for Fissile Class 'll shipment of Model 30 UF.. cylinders containing moderation controlled. uranium hexafluoride was developed at: the.0ak' Ridge. Gaseous Diffusion Plant.'
A high temperature phenolic foam plastic with -a fiber glass addi t ive. is.used as a fi re-resistant -material between the' liner and -shell.
Based on :the nuclear evaluation, ten of ' the packagings may be transported as a unit to a maximum 5.0 weight-percent U-235 enrichment.2 Engineering assessment (0ak Ridge) of the drop tes't and fire. damage to the prototype packaging resul ted 'in several design improvements which were incorporated into the. final 21PF-1 design.
An actual fire test was not conducted of - the modi fied design, however, based on the drop tests conducted, it was determined that any unit fabricated in.accordance with the modified design would provide considerably greater protection against fire ~ hazards.than the prototype tested.
The original 21PF-1 package was const ructed of carbon steel using tack welds (as opposed to full continuous welds) on the shell and angle sti f feners wi th a step-down gasket seal.
This design, being constructed of carbon steel, was susceptable to corrosion which was accelerated by water. retention behind angle stiffeners.
Water in-leakage was also observed due to the step-down gasket seal design.
A further design modi fication of the 21PlF-1 package was undertaken in order to correct the above identified problems.
To prevent water in-leakage, a step-up seal was provided.
Corrosion and rusting was elimir:ated by constructing the package entirely of stainless steel.
Full, continuous welds were also incorporated into the design for the shell and angle stif feners.
In addition, 14 uA stainless steel was used for the liner as opposed to 16 GA as used in previous designs.
The evolved package design, W-21PF-1, has been 'in use since 1983.
During this time, the packages have been free from damage and major maintenance.
Maintenance thus far has involved replacement of gaskets, pins and fasteners, in addi tion, water has never-leaked from or been observed inside these packages.
The packages, since being fabricated of SS304, have been corrosion free.
As a result of the packages (20) having been buiIt below the defined tolerance (81.60" 1 0.13"), the packages must be lengthened in order to accommodate UF. cylinders fabricated at the upper range of their tolerance.
The procedure for the W-21PF-1 modification to dimensional con fo rmance is described in Attachment Il-A.
In this attachment, a method is described for removing one end of the package and lenthening the package by the addi tion of 3" (typical) strips with 2"
backup bars of 14 GA SS304.
These backup bars provide weld reinforcement and container alignment prior to final welding.
Once repaired, % package is backfiiled with phenolic foam.
Acceptance eri terla for foam addition is given in Attachment 11-8.
This criteria will ensure correct foam density and weight.
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' Attachment IILC provides justi f.ication lfor_ a 0.15" reduction in the phenolic foam thickness as a resultiof :the: backup bars on the shell and liner.
Thi s - f oam reduction 'was shown to. be insignificant _ in'
~
terms of ca f ractional _ temperature increase based upon data;-provided.
in'the design basis thermal accident.
The ~ comparisori. also indicated
~
that the-cylinder' temperature will stillJ remain wi thin : the allowed -
service temperature of 250*F.
1.
A.
J.. Ma l l e t t. and - C.
.E.
Newlon, ' Protective Shippin~g Packages for 30-inch-Diameter UF. Cylinders, Union Carbide Corporation, Nuclear Division, 0ak Ridge Gaseous Diffusion Plant, K-1686 (April 13, 1967) 2.
C.
E.
Newlon and A.
J.
Mallett, Hydrogen Moderation ~- A Primary Nuclear Safety Control for. Handling and Transporting Low-Enrichment UF.,
Union Carbide Corporation,. Nuclear Division,- ' Oak-Ridge-Gaseous Diffusion Plant, K-1663 (May 31, 1966) 3.
Uranium Hexafluoride Handling Procedures and - Container Criteria, USAEC Report OR0-651.
Oak Ridge, Tenn:
Oak Ridge Operations Office, U.'S. Atomic Energy Commission,.May 1977, Revision 4.
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- 2.
- Reference Drawings 2.1 Drawing No. 360F05SE001, Sheet 1 of 4, Sub. 10 2.2 Drawing No. 360F05SE001, Sheet 2 of 4, Sub. 10 2.3 Drawing No. 360F05SE001, Sheet 3 of 4, Sub. 10 2.4 Drawing No. 360F05SE001, Sheet 4 of 4, Sub. 10 2.5 Orawing No. C2720045, Sheet 1 of 1, Sub. 7 l
Attachment il-A TITLE:
PROCEDURE FOR MODIFYING THE W-21PF-1 PROTECTIVE OVERPAKS TO DIMENSIONAL CONFORMANCE
REFERENCES:
1.
W lirawing No. 360F05E001, Sheets 1 through 4.
2.
AEC Material and Equipment Specification No. SP9, Rev.
1, for Fire Resistant Phenolic Foam as modified by Supplements 1/TL-729 (3/1/78) and K/P-6567 (4/28/80).
CERTIFICATION REQUIREMENTS:
1.
GTAW and GMAW Weld Procedures and Procedure Qualification per ASME Section IX.
2.
Welders to be qualified per ASME Section IX for all procedures used.
MATERIAL REQUIREMENTS:
1.
All stainless steel sheet material shall be ASTMA-240 Type 304 or 304L and shall be marked with its heat number and be traceable to its material test report as required above.
2.
Wood rails shall be made from select grade oak containing no more than 20% moisture.
3.
Wood glue shall be waterproof plastic resin glue (Weldwood or equal).
4.
Foam insulation shall be fire-resistant phenolic foam (with average density of 10 21 pcf) which is fabricued using materials and procedures per Reference #2.
5.
Vent hole seals stall be 1/4" polyethylene cap plugs (protective closures BPF-1/4 or equal).
6.
0-ring seals shall be neoprene 50-70 durometer Spec. AMS-3209 and shall be sized to properly fit the o-ring grooves (i.e. about 1" diameter cross section).
I PROCEDURE:
Step #1 Remove the 0-ring seals and then remove the formed side mating sur f ace plates (I tems 17 and 181 by grinding away welds inside and outside and at the mi ter joints joining the side and end mating surface plates; chisel to' break any residual welds.
Step #2 Cut inner 1iner (ltem 26) as shown in Figure 1 (2" from inside end); cutting may be by friction disc or plasma cutter.
-Step #3 Cut outer shell (Item #10) as shown in Figure 2 (2" f rom inside end); cutting may be by friction disc or plasma cutter.
Step #4 Saw through the wooden side rails at the cuts in the inner liner and outer shell; remove the end assembly.
j Step #5 Remove the foam to about a 2" depth from both exposed surfaces.
Step #6 Grind all cut stainless steel edges smooth and st raight, removing the heat affected zone of plasma cut edges.
I Step #7 Remove the remaining sections of wooden side rail from both the end ~ assembly
.and the side assembly.
Step #8: Roll form 14 GA Type '304 stainless steel strips.which, when welded into -the gaps in the inner liners, will make the inside length of each package ;82-5/8"
)
i 1/8".
See Figure 3.
Step #9 Roll. form 14 GA Type 304 stainless steel strips which when welde'd into the gaps in the outer shells, will make the outside shell length 91" 1/8".
See Figure 4 Step #10: Roll 2" wide, 14 GA, Type 304 stainless steel strips to be used as backing strips when welding in the inner. and outer filler strips f rom Step #8 and #9.
Tack weld backing strips to inner l!ner and outer shell on each side assembly as shown on Figures 3 and 4.
Step #11: Install new wooden side rail, cut to the correct length to correspond with an outer shell length of 91" 2 1/8".
Use new dowel rods and reglue the joints.
This rejoins the end and side assemblies leaving a void in the. foam insulation of approximately 5" and leaving approximately 1" gaps in the inner liner and outer shell where weld backing strips are in place for the installation of filler strips at these gaps.
Step #12: Weld filler strips f rom Step #8 and #9 as shown in Figures 3 and 4; use GTAW weld process, achieve 100% penetration, but limit. weld reinforcement to 1/32".
Step #13: Visually inspect welds in inner liners and outer shells for cracks or porosity; repair as needed.
Step #14: Form new side mating surface plates (ltems 17 & 18).of 10 GA Type 304 stainless steel and cut to the correct shape and length to match the 91" i 1/8" outer shells.
Step #15: Install the new plates from Step #14 and reweld using GMAW weld process; achieve 100% penetration at the mi tered joints w!th the end mat ing surface plates and 3/32" fillets at the inner liners and outer shells.
Step #16: Grind miter welds, flush and inspect all new welds for cracks and porosi ty; repair as needed.
Step #17: Cut 4" square hole in outer shell on either side at 45 f rom the centerline, and centered over the 5" void in the foam insulation resulting f rom Step #11.
Drill four (4) 1/4" diameter vent holes at fou r (4) circumferential locations in each half-section of the outer shell.
The four locations being 6 1/2" from the end of the outer shell, and centered in the two spaces between the angle rings of the outer shell.
The four holes at each of these ci rcumferential locations are as follows: one at each side 4" f rom the mating sur f ace, one at each side at 45* and one near the centerline.
Step #18: Make a 5" square cover plate f rom 14 GA Type 304 stainless steel for each 4" square hole cut in Step #17.
Drill eight (8) 1/8" rivet holes in each cover plate on 21/4" centers around the perimeter, and drill one (1) 1/4" vent hole in the center of each plate.
Roll form each plate to match the curvature of the outer shell.
Match drill the 1/8" rivet holes at each 4" square hole in the outer shell.
i
w Step #19: Reinsulate the '5" void (see Attachment 11-8) created in Step #11 wi th Phenolic Foam-at a density of 10 il pcf per AEC Specification SP9 (see Material Requi rements i tem #4); install the foam through the 4" square holes f rom Step
- 17.
Step #20: Immediately following Step #19, cover the 4" square holes by pop riveting a 5" square cover plate over each hole; use eight- (8) stainless steel pop rivets for each cover.
Step #21: After foaming operation.is complete.
inspect the five (5) vent holes associated with newly installed foam to insure the foam has proper.ly filled the entire void; refoam as needed.
Step #22: Seal weld each cover plate installed in Step #20 using GTAW weld process.
Visually inspect all cover plate weids for cracks and porosi ty; repair as needed.
Step #23: Seal all 1/4" vent holes in each package half-section with ~RTV silirone caulking and 1/4" plastic cap plugs. See Material Requirements item #5.
Step #24: Sandblast all new metal surfaces to catch existing metal surfaces.
Step #25: Install new 0-ring seals (see Material Requirements i tem #6) of the correct j
t length and assemble the package; inspect the seals and overall fit up, ATTACHMENTS:
1.
Figure 1 and Figure 2 2.
Figure 3 and Figure 4 i
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PROCEDURE FOR MODIFY 1NG THE UF ' SHIPPING CONTAINERS TO DIMENSIONAL CONFORMANCE 6
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Attachment Il-B
' TITLE:
ACCEPTANCE' CRITERI A - FOR PHEN 0LIC F0AM ADDITIONS TO MODIFIED W-21Pl 1 UF.
SHIPPING CONTAINER
REFERENCES:
1.
W Drawing No. 360F05E001', Sheets 1'through 4.
2.
AEC Material and Equipment Speci fication.No.
SP9, Rev,
-1
,for Fire Resistant Phenolic Foam as modified by Supplements 1/TL-729-(3/1/78) and K/P-6567 (4/29/80).
MATERIAL REQUIREMENTS 1.
Foam insulation shall be fire resistant phenolic foam (with ~ average density of 10 i pcf) which is fabricated using materials and procedures per Reference #2.
2.
4" diameter PVC pipe, or approved equal, wi th one end but ted, tare weighed to an accuracyof0.1%(topeusedforfoamdensitycheck).
DENSITY ACCEPTANCE CRITERIA:
I 1.
Select a simple geometry pipe with butted end.
2.
Determine volume to which foam can occupy based on pipe dimensions.
3.
Tare' weigh pipe to an accuracy of i 0.1%.
1.
Pour foam in pipe.
5.
After foaming has sot, gross weigh to an accuracy of i 0.1%.
6.
Determine the net weight of foam added by gross and tare weight comparisons.
7.
Calculate the density of the foam in the pipe based on a net foam weight and pipe volume comparison.
8.
Foam density shall meet Material Requirements #1 prior to foaming of containers, j
W-21PF-1 FOAM WElGHT ACCEPTANCE CRITERIA, 1.
Based on the depth of the foam void, calulate the volume for foam addition and determine the weight to be added to each overpak.
2.
Tare weigh each section of modi fied W-21PF-1 overpak. to an accuracy of f 0.1% prior to addition of foam.
3.
After density acceptance criteria has been established, foam top and bottom of container in accordance with procedure described in Attachment Il-A.
i 4.
After foam has set, gross weigh each section of overpak (prior to vent plug replacement) to an accuracy of 1 0.1%.
i 5.
Determine net weight of foam addition to each section by gross and tare weight comparisons.
i 6.
Determine the deviation of measured-to-calculated foam weights.
Deviation shall be less than i 10%.
.Attachmant-l'liC
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' JUSTIFICATION FOR REDUCTION OF-PHENOLIC F0AM BY:
-0.15" ALONG A 2" STRIP.
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DESCRIPTION-
'This analysis. involves:a calcul'at ion -requi ring Fourier's' equation forf-a -
plane wall for steady-state' conditions ~,
-11.
CRITERIA:
-i; Fourier's Equation: 0 = -KA AT 6 L.
where-0'is the heat conducted into a volume-element, K is the-heat capacity constant, A is the cross-sectionalz area.
and A T/d L is the temperature di f ferential, q
.ii.
A X,, d Ti, represent the : full ~ foam ; thickness and - temperature-differential (6 Xi = 6").
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d-X,.
4 T2 represent the reduced foam thickness and 2
temperature differential ( A X '= 6 Xi -0.15).
i iv. Or = 0, for steady state conditions.
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i III. CALCULATI0t6:
1.
Q1 = Q2 AT1 = RA AT2 2.
-kA 6L1 AL2 6T1 = KA d 2 3.
6L1 oL2 4.
AT1 AL2=dT2 6L1 5.
6X2= 6X1 - 0.15 6.
6T1(6XI - 0.15) = AT2 6X1 7.
6T1 AXI-AT1 (0.15) = 4T26X1 8.
4X1(4T1-4T)= AT1 (0.15) 2 AT1-6T2
_ 0.15 9,
T1 o x1 d
1- 0 2 10.
0.025, Fractional Temperature Increase
=
oT1
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IV. CONCLUSIONS:
a
'Since the average temperature of the inner cylinder for the design 2
basis fire test
.vas about 200*F, the 2.5% increase is insigni ficant -
in terms of an actual temperature increase.
Based on this analysis, the inner UF. cylinder, within the W-21PF-1 package, will remain wi thin the 2.50*F maximum permissible temperature as defined in OR0-651.