ML20045G310
| ML20045G310 | |
| Person / Time | |
|---|---|
| Issue date: | 06/21/1993 |
| From: | Withee C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9307130170 | |
| Download: ML20045G310 (10) | |
Text
Juli 21 1%3, Distribution:
IMTB:CJW INRC.FC NMSS r/f IMTB r/f Attendees w/o encl MEMORANDUM FOR:
The File gNRC.PDR g Meeting Notebook FROM:
Carl J. Withee, IMTB/IMNS/NMSS
SUBJECT:
PRE-APPLICATION MEETING
SUMMARY
CONCERNING MODEL NO. 3300 PACKAGE Attendees NRC AMERSHAM l
Carl Withee Bryan Baker Henry Lee Kyle Karsten Nancy Osgood Kate Roughan Bernie White Li Yang Introduction A meeting was held at the request of Amersham Corporation at Rockville, Maryland, on June 17, 1993, to discuss the Model No. 3300 shipping package.
A copy of the meeting agenda is attached.
Discussion Amersham gave a description of the packaging and the proposed contents. A discussion was held on the planned application and the type of information to be supplied.
The QA plan of the corporate office in Burlington, MA will be used for the package design, testing and fabrication.
The applicant was cautioned about the potential difficulty in scaling test results from the Model No. 3100 design in lieu of testing the Model No. 3300 design directly.
An application is not expected until 1994.
Carl J. Withee Transportation Branch Division of Industrial and Medical Nuclear Safety, NMSS
Attachment:
Meeting Agenda 0FC IMTB C
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Jus 21 1M 1MTB:CJW MEMORANDUM FOR:
The File FROM:
Carl J. Withee, IMTB/IMNS/NMSS
SUBJECT:
PRE-APPLICATION MEETING
SUMMARY
CONCERNING MODEL NO. 3300 PACKAGE Attendees NRC AMERSHAM l
l Carl Withee Bryan Baker Henry Lee Kyle Karsten Nancy Osgood Kate Roughan Bernie White l
Li Yang l
Introduction A meeting was held at the request of Amersham Corporation at Rockville, Maryland, on June 17, 1993, to discuss the Model No. 3300 shipping package. A copy of the meeting agenda is attached.
l Discussion Amersham gave a description of the packaging and the proposed contents.
A discussion was held on the planned application and the type of information to be supplied.
The QA plan of the corporate office in Burlington, MA will be used for the package design, testing and fabrication. The applicant was cautioned about the potential difficulty in scaling test results from the Model No. 3100 design in lieu of testing the Model No. 3300 design directly.
An application is not expected until 1994.
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C( Q Carl JYWithee Transportation Branch Division of Industrial and Medical Nuclear Safety, NMSS
Attachment:
Meeting Agenda i
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AGENDA FOR 3300A TYPE B(U) PACKAGING MEETING Thursday, June 17,1993 1.
Design Criteria 2.
Description of Package Dimensions and Weight Component Materials (parts list)
Fabrication Methods i
Operational Features l
3.
Contents of Package l
Radionuclides
. Activity Form Decay Heat 1
l 4.
Package Evaluation Margin of Safety Model Testing i
5.
Description of Application 6.
Quality Assurance Requirements Availability of Documentation l
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1.0 DESIGN CRITERIA Activity: 540,000 Curies Type of Energy: Gamma Size of Capsule:
18"long x 0.3937" diameter Operational for Wet Imading Meet regulatory requirements for Normal and Hypothetical Accident Conditions 2.0 PACKAGE DESCRWTION 1
Dimensions: 54" x 54" x 54" Weight:
7898 lbs.
2.1 Components Pallet:
Stainless Steel Outer Framework: Stainless Steel Body:
Stainless Steel / Depleted Uranium Closure:
Stainless Steel / Depleted Uranium Maintenance Plug: Stainless Steel Drain Plug:
Stainless Steel Cover:
Stainless Steel Hex Head Screw M20 x 45 mm lang BS 3592 Stainless Steel BS 6105 Grade A2 - 70 i
Hex Head Screw M16 x 40 mm long Steel BS 3692 Grade 8.8 l
l Washer M20 Form A BS 4320 Stainless Steel Washer M16 Form A BS 4320 Stainless Steel Hex Skt Button HD Screw M4 x 6 mm long I
Stainless Steel BS 4168 PT 6 M30 Collar Eyebolt to BS 4278 Stainless Steel Drain Tube - 9.53 O/D x 1.63 Wall Stainless Steel Seamless Tube ASTM A269 316L l
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2.2 Fabrications Methods British Standards BS 499 Part 2,1980:
Welding terms and syrnbols BS 4870 Part 1,1981:
Approval testing of welding procedures.
BS 4871 Part 1,1982:
Approval testing of welders BS 6072,1981:
Magnetic particle flaw detection BS 2600,1973:
Radiographic examination of fusion welds BS 3923 Part 1,1978:
Ultrasonic examination of fusion welds BS 131 Part 2,1972:
Notched bar testing 2.3 Operational Features Mesh Cage
- Protection from hot surfaces
- Free air flow
- Handling Wet or Dry Loading Eight M20 Bolts for Closure Cover l
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Variety of Capsule Holders - 25,32,42,56 Capacities
3.0 CONTENTS OF PACKAGE Nuclide Physical Chemical State Activity Activity Nuclear Decay State (PBq)
(kCi)
Heating Heat (mW/Ci)
(watts)
Co-60 solid Metal /Co 20.0 540 15.4 8,316 Cs-137 solid Chloride /CsCl 3.70 100 4.48 448 Ir-192 solid Metal /Ir 3.70 100 5.85 585 Eu-152 solid Oxide /Eu2O 0.835 22.5 7.37 166 3
Eu-154 solid Oxide /Eu20 0.702 18.9 8.78 166 3
Eu-155 solid Oxide /Eu20 9.220 248.9 0.67 167 3
Eu-156 solid Oxide /Eu20 0.606 16.4 10.19 167 3
9.780 263.1 0.63 166 Gd-153 solid Oxide /Gd 03 2
4.0 PACKAGE EVALUATION 4.1 Structural - IPM 024 Issue 1, Page 6 of 8,5. a) 4.2 Thermal The fire test was simulated using the TAU finite element program developed and run by Risley Nuclear Power Development Establishment, United Kingdom Atomic Energy Authority (Northern Division), Risley, Warrington, WA3 6AT.
4.2.1 Accentance Criteria for Thermal Evaluation:
4.2.1.1 Capsule temperature can not exceed 800 C.
4.2.1.2 Temperature at any uranium / stainless steel interface must not exceed 760 *C (the lowest possible temperature for an alloy to be formed).
Inner Surface of the cavity is calculated by the TAU program to be 522 *C. The estimated temperature of the inner most capsule is 697 C which is well under 800 C.
Inner Surface of the jacket is calculated by the TAU program to be 458 *C.
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4.2.2 Suonorting Documents:
ND R-556(R), Revision 1, Validation Cases for TAU, a heat transfer program in the UNCLE System, October 1986.
ND-R-218(R), Revision 2, TAU: A computer program for the analysis of the temperature in two and three dimensional structures using the UNCLE finite element scheme, June 1986.
l SESD Note 310, An analysis of the NEACRP Heat Transfer Benchmark Tests Using TAU, RIGG and FLUFF Codes, September 1985.
4.2.3 Validation
K At ambient (20 *C) with 11.2 PBq (302.4 Ci)
TAU:
Fin Mid-Height Surface Temperature of 127 C Closure Center Surface Temperature of 100 *C Measured temperatures with Hermet visual temperature indicators (accuracy within 1.5 C).
Fin Mid-Height Surface Temperature of 128 *C Closure Center Surface Temperature of 113 *C 4.3 Shielding 4.3.1 Shielding Material and Thickness:
Depleted Uranium - 156 mm Stainless Steel - 23 mm 4.3.2 Melting Points of Material Depleted Uranium - 1,132 C Stainless Steel - 1,450 *C 4.3.3 Maximum Radiation Levels Surface of the Package 14 mR/hr One Meter from the Package - 3.7 mR/hr 4
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IPM 024 Issue 1 page 6 of 8
- 941*K - 668'c The safety margin is thus 668 - 522 - 146*C.
To put this in perspective the safety margin is greater than the temperature rise of the flask cavity during l
the fire test (522 - 384 - 138'C).
c) Temperature of DU/SS Interface IPM 023 concludes that the peak component temperature of any depleted uranium / stainless steel interface is 488/512*C. This is safely below the l
temperature at which a eutectic alloy could theoretically form (760*C).
There is no need therefore for any barrier between the two materials d) Programme confirmation IPM 031 shows that the steady state flask surface temperature was accurately predicted by the computer programme. This not only confirms the flask's initial conditions at the start of the thermal test but also i
gives additional confidence in the programme accuracy.
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MECHANICAL PERFORMANCE f
a)
Structural Modifications:
1 The 3300 flask incorporates the folicsing structural modifications from l
the design of the 3100 model:-
(i) The cooling fins are 500% wider (175mm from 35mm), 600% thicker (3/8" from 1/16") and ate formed in pairs as a round bottomed "V" (ii) The body outer skin is 582% thicker (19.5mm from 3.35mm).
(iii)The body bottom skin is 1,540s thicker (50mm from 3.25mm).
(iv) The body shielding pieces have a 347% greater inside diameter (133mm from 38.3mm and an 334% greater outside diameter (459mm from 137.3mm).
(v) The closure shock absorbing fins are 436% higher (61mm from 14mm),
347% longer (275mm from 79.2mm) and 300% thicker (3/8" from 1/8").
(vi) The fastenings holding the jacket onto the body have been strengthened by using screws in three places onto each of the four thick fins.
(vii)The weight of the assembly plus contents has increased by 3,860%
(3,590 kg from 93.0 kg, equivalent to 3.38 linear).
(viii) The weight of closure plus contents has increased by 2,940% (297kg from 10.1 kg, equivalent to 3.09 linear).
(ix) The weight of the flask and contents has increased by 3,800t (3,170 kg from S3.4 kg, equivalent to 3.36 linear).
(x) ThesizeofclosureboltshasincreasedfromM6 tom 20givgngan increase in tensile stress area of 12,190% (20.1 to 245 mm, ref BS 3692, equivalent to 3.49 linear).
b) Effect of Modifications on Mechanical Test Results l
(i) IPM 010 (9m angled base drop)
The force of the primary impact was absorbed almost entirely by the edge of the pallet. When the flask broke free from its mountings the two lower flask feet became slightly twisted and the outer framework became buckled through secondary. flask impacts. As all the mndifications above have made the flask stronger and heavier the
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