ML20027D230
| ML20027D230 | |
| Person / Time | |
|---|---|
| Site: | 07109086 |
| Issue date: | 09/22/1982 |
| From: | Mallory C HITTMAN NUCLEAR & DEVELOPMENT CORP. (SUBS. OF HITTMAN |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20027D231 | List: |
| References | |
| 21289, HN-E642, NUDOCS 8211030378 | |
| Download: ML20027D230 (17) | |
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C, September 22, 1982 o,
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Mr. Charles MacDonald 2-Chief, Transportation Branch Z
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ogp%,p Subj ect:
HNDC HN-100 Series 1 C,
P Radioactive Materials Package 4
,j Certificate of Compliance No. 71-9086 Application for Revewal
Dear Mr. MacDonald:
In response to your August 27, 1982 letter (FCTC:CEW, 71-9086), attached are eight copies of the following:
(1) Attachment A, " Responses to Nuclear Regulatory Commission Letter dated August 27, 1982."
(2) Attachment B through Attachment C.
Replacement pages for
" Safety Analysis Report for the HN-100 Series 1 Radwaste Shipping Cask", STD-R-02-006, Revision 0.
(3) Hittman Nuclear & Development Corporation Drawing Nos. :
STD-02-028, Revision 4 ;
STD-02-029, Revision 4; and STD-02-030, Revision 3.
Attachment A describes the changes which have been made in the Safety Analysis Report and drawings to provide the information requested by your letter.
If the attached information is found to be acceptable, H1TTMAN will revise and issue the Safety Analysis Report to provide a consolidated document for use by your office and the registered users of the package.
H1TTMAN recognizes that the attached information which is stamped
" Proprietary" will be placed in the Nuclear Regulatory Commission Public Document Room. Attachment H is a notice relative to the further dissem-ination and use of this information which must remain on file with this material.
79 F*i W
- a 8211030378 820922
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J b$ o h Page 2 Mr. Charles MacDonald September 22, 1982 The fee for the renewal of this application was forwarded by our letter of April 9, 1982.
If you have any questions or require additional infor-mation, please contact me.
Very truly yours, s
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b C 3rles W.
C Vice Preside Engineering Ih Attachments 4
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" Y~(({lf 0 __Jh5o h ATTACHMENT A Radioactive Materials Package Certificate of Compliance No. 9086 HNDC Model HN-100 Series 2 Application for Renewal September 22, 1982
" Responses to Nuclear Regulatory Commission Letter dated August 27, 1982" A.
GENERAL The attached replacement pages to the " Safety Analysis Report for the HN-100 Series 1 Radwaste Shipping Cask", STD-R-02-006, Revision 0 and the following revised drawings are submitted in response to the Nuclear Regulatory Commission letter, FCTC:CEW, 71-9086 dated August 27, 1982:
Hittman Nuclear & Development Corporation Drawing Nos.:
STD-02-028, Revision 4 ;
STD-02-029, Revision 4; and STD-02-030, Revision 3.
B.
SPECIFIC COMMENTS 1.
Cask Dimensions and Lift Lugs Replacement page 1-2 (Attachment B) and drawing no. STD-02-028, Revision 4 have been revised to provide consistent dimensions based on as-built drawings. Drawing no. STD-02-029, Revision 4, has been revised to make the lift lug options consistent with designations used on page 2-1 of the Safety Analysis Report.
2.
Mounting Plate Weld Replacement pages 2-46 and 2-47 (Attachment C) contain an analysis of the weld attaching the reinforcing plate to the cask shell which shows the weld to be adequate.
3.
Repair of Tapped Holes Replacement pages 4-5, 4-6 and 4-7 (Attachment D) contain an analysis of the various stud repair options which shows the repair procedures to be structurally equivalent to the basic design.
4.
Direct Impact on Drain Plug Since the present drain plug protrudes outside of the shell, the outer portion of the plug would be crushed on direct impact. The portion of the plug within the shell should remain intact and should maintain the integrity of the container.
Since this cannot be readily demonstrated by analysis, the drain plug design has been revised ao shown
b Page 2 ATTACHMENT A September 22, 1982 in Section D-D on drawing no. STD-02-028, Revision 4 and Section F-F on drawing no. STD-02-030, Revision 3.
The new design will be a recessed plug which will be protected by the shell. The drain plugs will be modified over the next four months.-
1 5.
Drawing Comments a.
Weld Efficiency Paragraph 2.1.2.3 on replacement page 2-4 (Attachment E) has been revised to indicate that a weld efficiency of 85 percent has been included in the analysis of welds for conservatism y
since complete records of NDE inspections are not available.
Drawing nos. STD-02-028 and STD-02-029 have been revised to show the welds reported to have been NDE inspected on the manufacturer's drawings. A note has been added to the drawing covering the inspection requirements for future welding on these packages or fabrication of new packages.
I b.
Material Specifications
[-
Table 2.3.1 and Table 2.3.3 on replacement pages 2-6 and 2-7 (Attachment F) have been revised to clarify that steel specified for the cask body applies to the outer shell. The Bill of Material on drawings nos. STD-02-028 and STD-02-029 have been modified to include the minimum strength and mechanical proper-ties called for in the Safety Analysis Report and the design.
c.
Reference Dimensions i
Drawing nos. STD-02-028 and STD-02-029 have been revised to remove " reference" from the dimensions used in the Safety Analysis i
Report. The as-built drawings have been reviewed to assure that l
the actual dimensions are within the tolerances specified in the title block. Where dimensions are not within specified tolerance, the actual tolerance has been added to the dimensions.
1 d.
Weld Symbols l
Drawing nos. STD-02-028 and STD-02-029 have been revised to remove nonconforming weld symbols. A note has been added referencing the weld symbol to the AWS Code.
e.
Welding Codes Notes have been added to drawings nos. STD-02-028 and STD-02-029 referencing welding to ASME Section III, crc; ASME Section IX or AWS.
i
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Page 3 ATTACHMENT A September 22, 1982 f.
Drawing No. STD-02-028, Revision 4 The tolerance on the cask I.D. is now in agreement for Zones D-8 and C-1.
The tie-down lug has been dimensionally located in the plan view and view f-f.
The lid closure flange has been designated as Item 14 on drawing STD-02-028 and is included on the Bill of Material.
The depth of the flange has been dimensioned.
g.
Option 1 Lift Lug The thickness of Item 8 on drawing no. STD-02-029, Revision 4 is now specified.
h.
Cask Height Drawing no. STD-02-028 has been revised to show a height of 82 inches to agree with drawing STD-02-029.
C.
OTHER SAFETY ANALYSIS REPORT CHANGES Replacement pages 4-3 and 4-4 (Attachment G) correct typographical errors in the prior submittal.
D.
REQUESTED CHANGES TO CERTIFICATE OF COMPLIANCE NO. 71-9086 a
The changes in the Certificate of Compliance should be as requested in i
paragraph D of Attachment A to Hittman Nuclear & Development Corporation letter HN-E630, dated July 23, 1982, except as follows:
i Paragraph 5(a)(2)
"A steel encased, lead shielded cask for low opecific activity material.
The cask is a right circular cylinder 82.5 inches high by 82 inches in diameter. The cask cavity is 74.5 inches high by 75.625 inches in diameter....."
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ATTACHMENT B The llN-100 Series 1 Shipping Cask is a primary containment vessel for radioactive materials.
It consists of a cask body, cask lid, and a shield plug being basically a top-opening right circular cylinder which is on its vertical axis.
Its principal dimensions are 82 inches outside shell diameter by 82.5 inches high with internal cavity of 75.625 inches inside diameter by 74.5 inches high.
1.2.1.1 Cask Hody, The cask body is a steel-lead-steel annulus in the form of a vertical oriented, right circular cylinder closed on the bottom end.
The cask is a right circular cylinder 82.5 inches high by 82 inches in diameter. The cask cavity is 74.5 inches high by 75.625 inches in diamater. The cask side wall consists of a 3/8-inch thick inner steel shell, a 1-3/4-inch lead shell, and a 7/8-inch thick outer steel sheli. The base is a 4-inch thick steel plate which is welded to the inner and outer steel shells of the side wall. A steel flange is welded to the inner and outer steel shells of the side wall to the top.
The lid is a 4-inch thick steel plate which is stepped to mate with the steel flange. The cask closure is sealed by a Viton or BUNA-N 0-ring gasket located between the lid and steel flange.
Positive lid closure is accomplished by thirty, 1-inch studs. The lid contains a centrally located 4-inch thick stepped steel shield plug. The shield plug is sealed by a Viton or BUNA-N 0-ring gasket, and sixteen,,1/2-inch studs are used to pro-vide positive closure. Tie-down is accomplished by four tie-down lugs welded to the cask body. There are two or three casks lifting lugs, three lid lugs, and one shield plug lifting lug.
1.2.1.2 Cask 1.id The cask lid is four inches thick which is stepped to mate with the upper flange of the cask body and its closure seal. Three steel lif ting lugs are welded to the cask lid for handling. The cask lid also contains stepped opening for a shield plug at its center.
1-2
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PROPRIEIARY DATA imc-sr c Bearing 78,500 x 2.75 x 1.44 = 310,860 lbs Tensile 78,500 x (3.75-1.56) x 1.44 = 247,558 lbs Accordingly, a tensile failure of the lug will occur before the cask shell is damaged.
2.10.2.15 Tiedown Refinforcing Plate Weld 13" 11.75" CG
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CG 211,766 lb Neutral Axis 2-46
PROPRIETARY DATA
^tacn-" c Shear os = 211,766 lb/(4)(13)(0.75)(0.85)(sin 45 )
os = 9034 psi Bending Moment = (211,766 lb) (1.75) = 370,590 in/lb.
370,590 = 2 OB [(11.75)(6.1)( )+(14.53)(5.6)( )-(1.53)(.625)( )+
(1.25)(.65)( )]
(0.75)(0.85)(sin 45 )
= 5376 psi
/ 2 2
10,512 psi SF.=2.0 OT = VoB +oS
=
2.10.3
, Free Drop Since the package weighs in excess of 30,000 lbs., it must be able to withstand a one foot drop on any surface, without loss of contents.
2.10.3.1 One Fool Drop on Bottom Corner Energy to be absorbed = 50,000 lb x 12 in.
5 Maximum energy = 6 x 10 in. lb Energy will be absorbed by crushing of corner.
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Bottom Steel 4" Thick Plate It 2-47
PROPRIETARY DATA
^ " " ' " " " '
I Added to the pre-load tension 100.3 + 6400 = 6500 lb/ stud 6 = PL/AE = (6500)(1.25)/(.4041)2(n/4)(29x10 )
6
=.0022 in s,
t This distance is too small to break the seal and signficantly reduce the package effectiveness.
4.2.2 Pressurization of Containment Vessel Due to the nature pf the waste contents, no vapors or gases could form to pressurize the vessel and significantly reduce the package ef-fectiveness.
4.2.3 p olant Contamination
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The vessel contains no primary coolant, therefore this section is not applicable.
4.2.4 Coolant Loss x
The vessel contains no primary coolant, therefore this section does not apply.
'l 4.2.5 Repair of Primary and Secondary Lid lloid-downs The possible repair procedures listed on th'e' referenced drawing provide 3 methods of repairing or replacing a. stud by modifying the tapped hole. s.In SL1, cases, the hidification provides an
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T as-strong or stronger assembly than h'e original design.
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ATTACl! MENT D PROPRIEIAliY DATA "A.
Heli-coil Insert" -
The Helf-coi18 insert consists of a helical wound wire (diamond i
shaped cross-section) which reduces the threads of a slightly over-sized tapped hole. As shown below, the Heli-coi1@ assembly has a higher yield load point than the stud.
Primary Lid - According to the manufacturer of Heli-coils 6, a 1 inch diameter Heli-coile inserted 1 inches has a tensile load of 108,000 lb.
The 1" A193 or A320 Gr 7 stud has a tensile load of 76,000 lb.
Secondary Lid - Similarly,
" diameter Heli-coi18 inserted 1 inch has a tensile load of 37,500 lb., the " stud is 18,000 lb.
"B - Increase depth of tap drill and retap appropriate length" This method of repair includes using the same diameter stud, however 1
increasing its length. The question to be addressed is to determine the increased clongation from torquing and internal pressure (4.2.1 7
of SAR).
The primary lid stud tension from initial torquing and an internal pressure of 7.5 psig is 17,920 lb./ stud.
If the length of the stud is increased from 2.25 in. to 3.25 in., a difference of an inch, the elongation will be:
6 PL _ (17,920 lb)(3.25 in.) - 0.0036 in.
AE
(.844)2 (U/4)(29x10 )
6 Similarly, the secondary lid stud tension (total) is 6500 lb./ stud.
If the length of the stud is increased from 1.25 in. to 2.25 in.,
6 PL _
(6500)(2.25)
- 0.004 in.
6 AE
(.4041)2(H/4)(29x10 )
4-6
=
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ATTACllMENT D j
PROPRIETARY DATA i
i i
Both clongations claculated are very small and not enough to break 4 -
-the gasket. seal and significantly reduce the package effectiveness.
i "C.
Drill and Tap (1/8" larger diam.) NC - Rebore hole in(primary /
l secondary) lid for clearance."
4 Replacing the present stud with a. larger diameter improves the
.i strength of the lid hold downs.
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I j-4.3 Containment Hequirements for the Ilypothetical i
Accident Conditions 1
This section does not apply since the vessel is not a. type B pack-a age.
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ATTAC11MF.NT E ETMY TA found by dividing the minimum yield by the calculated stress. A safety factor greater than 1.0 is required for acceptability.
See Table 2.3.3 for minimum yleid and ultimate stress values used in the analyis.
2.1.2.2 Stresses in material due to shearing is analyzed using the
" Maximum Energy - Distortion Theory" which states the shearing clastic limit is 1//3 = 57.7% of the tensile i
elastic limit. As with 3.1.3.1, a factor of safety greater than 1.0 is required for acceptability.
2.1.2.3 Weld filler material rod is E70 Grade. Analysis is based on American Welding Society Structural Code D1.1-79.
For fillet welds, shear stress on effective throat regardless of direction of loading is 30% of specified minimum ten-sile strength of weld metal. For complete joint pene-tration groove welds with tension normal to the effective area the allowable stress is the same as the base metal.
Fillet weld allowable stress = (68,750 psi) (0.3)
= 20,625 psi In order to be more conservative, a weld efficiency of 85%
is also added since not all weld have been nondestruc-tively examined.
2.2 Weights and Centers of Gravity 2.2.1 Gross Package Weights The respective gross weights of the cask components and its designated radwaste loads are as follows:
2-4
TABLE 2.3.1 MATERIALS OF CONSTRUCTION (Certified Minimum Yield / Ultimate Strength, psi)
HNDC HN-100 Series 1 FMDWASTE SHIPPING CASKS d
M Unit Cask Tiedown Lift 5
Number Body (outer shell)
Lugs Lugs
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HN-100-1 A516, Grade 55 A203, Grade E A516, Grade 60 (42,000/64,800)
(61,100/78,500)
(52,000/71,000)
HN-100-2 A516, Grade 55 A203, Grade E A516, Grade 60 (42,000/64,800)
(61,100/78,500)
(52,000/71,000) s, HN-100-3 A516, Grade 55 A203, Grade E A203, Grade E (50,700/64,000)
(61,100/78,500) 61,200/77,300 HN-100-4 A516, Grade 55 A203, Grade E A203, Grade E (43,000/64,800)
(61,100/78,500)
(58,300/81,900)
T HN-100-5 A515, Grade 70 A515, Grade 70*
A515, Grade 70 EE3 (45,100/75,600)
(50,400/79,300)
(43,900/75,100) t2 F55 r
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PROPRIETARY DATA ArrACunenT r struct. ion of the cask bodies, lif t lugn and tiedown lugs. Table 2.3.2 lists the minimum yield and ultimate st rength of materials based on ASTM Standards. Table 2.3.1 also lists the certified yield and ultimate strength of the materials used in t.he critical components of the cask.
These are significantly higher than the minimal values based on ASTM Standards. Table 2.3.3 lists the values for minimum yield and ultimate strength used in analysis of critical components. ror non-critical components, the values listed in Table.2.3.2 were used for analysis. The weld filler material used in the casks has a minimum ultimate strength of 68,750 psi.
Table 2.3.2 Minimum Yield and Ultimate St.rength Based on ASTM Standards MATERIAL YIELD STRENGTil ULTIMATE STRENGTil (psi)
(psi)
A516, Grade 55 30,000 55,000 A203, Grade E 40,000 70,000 A515, Grade 70 38,000 70,000 Table 2.3.3 Minimum Yield and Ultimate Strength Used in the Analysis of Critical Components Minimum Yield Ultimate Strength (psi)
(psi)
Cask Ilody (outer shell) 42,000 64,800 Tic-Down Lugs 61,100*
78,500 Lift Lugs 43,900 71,000
- A minimum yield of 50,400 psi is used for the llN-100 Series 1, Unit No.
5.
2-7
ATTACllM".NT C PROPRIETARY DATA 1
Total force exerted on the gasket ring is:
(30)(16,800) + 6500 = 510,500 lb Area of "0" Ring = (78 in) (n)(1/2 in) = 122.5 in2 Total pressure on gasket material 510,500/122.5 in2 = 4166 psi The torquing procedure values ensure that there is sufficient pres-sure.on the gasket to seal the cask.
Similarly, the shield plug torquing requirement is 35 to 40 ft-lb.
F = (40 ft-lb)(12 in/ft)/(0.15)(0.5 in) 3 1
F = 6400 lb/ stud.
i Weight of the shield plug is 500 lb.
Total force on shield plug gasket is (6400 lb)(16 studs) + 500 = 102,900 lb.
Area of gasket = (18.125)(n)(.375) = 21.35 in2 Pressure on gasket = 102,900/21.35
= 4820 psi This is sufficient to maintain the gasket seal.
4-3
A'!TACllMlWT (;
PROPRIETARY DATA 4.2 Requirements for Normal Conditions of Transport 4.2.1 Release of Radioactive flaterial An internal pressure of 7.5 psig is the normal condition that may cause a release of radioactive material.
The force exerted on the primary lid from a 1/2 an atmosphere dif-ferential pressure is:
(7.5 lb/in ) (75.5 in)2(n/4) = 33,577 lb 2
on a per stud basis, 33,577 lb/30 studs = 1120 lb/ stud Add this force to the pre load, 1120 + 16,800 = 17,920 lb.
6 = Eb = (17,920 lb)(2.25 in) - 0'0025 in 8
AE
(.844)Z(n/4)(29 x 10 )
This is very small and not enough to break the gasket seal and signifi-l cantly reduce the package effectiveness.
Similarly, the shield plug experiences a force of 2
(7.5 lb/in )(16.5 in)2(n/4) = 1605 lb On a per stud basis, i
1605 lb/16 studs = 100.3 lb/ bolt a
4-4
ATTACHMENT H PROPRIETARY DATA NOTICE This Safety Analysis Report and the associated drawings are the property of Hittman Nuclear & Development Corporation,
- Columbia, Maryland.
This material is being made available for the purpose of obtaining required certifications by the U. S.
Nuclear Regulatory Commission, enabling utilities and other firms producing radioactive waste to be registered users of equipment and services supplied by Hittman Nuclear &
Development Corporation, and enabling equipment to be manufactured on behalf of and under contracts with Hittman Nuclear & Development Corporation.
Parties who may come into possession of this material are cautioned that the information is PROPRIETARY to the interests of Hittman Nuclear & Development Corporation, is not to be reproduced from tiiis report and the associated drawings, or facsimiles made of these drawings without the express written consent of the Hittman Nuclear & Development Corporation.
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