ML19261E547
| ML19261E547 | |
| Person / Time | |
|---|---|
| Site: | 07109134 |
| Issue date: | 08/08/1979 |
| From: | Williams C ENERGY, DEPT. OF |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| PR-T-79-012, PR-T-79-12, NUDOCS 7908280853 | |
| Download: ML19261E547 (24) | |
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Mr. Charles E. MacDonald, Chief Transportation Branch s
Division of Fuel Cycle and Material Safety U. S. Nuclear Regulatory Connission Washington D.C.
20555
Subject:
REQUEST FOR APPROVAL OF THE ETR FUEL ELEMENT SHIPPING CONTAINERS
Dear Mr. MacDonald:
The U. S. Department of Energy (DOE), Idaho Operations Office (ID), has approved the use of the ETR Fuel Element Shipping Container for the shipment of Type A quantities of unirradiated ETR and GETR fuel elements.
The subject container is similar in design to the ATR Fuel Element Shipping Container, previously approved by ID under Certificate of Compliance USA /5705/AF(ERDA-ID) and by NRC under Certificate of Compliance USA /9099/AF.
Therefore, we have issued USA /5705/AF(DOE-ID), Revision 1, to include the ETR Fuel Element Shipping Container.
In accordance with guidance provided ID (S. W. Farkas, OSD) by T. L. Dunckel, Division of Operational and Environmental Safety (0&ES), DOE Headquarters, eight (8) copies of the following documents are enclosed to facilitate and expedite NRC review:
1.
EG&G Idaho, Inc., Report No. PR-T-79-012, ETR Fuel Element Shioping Container, dated August 7,1979 - Addendum to PR-T-79-Oll (TR-466).
2.
DOE Certificate of Compliance, USA /5705/AF(00E-ID) Revision 1, issued for use of the ATR and ETR Fuel Element Shipping Containers, dated F
August 1979.
3.
DOE-ID Sunnary Evaluation for the ETR Fuel Element Shipping Container, dated August 1979.
j Because of safety considerations, the General Electric Co., Vallecitos f
Nuclear Center, Pleasanton, California, has requested the use of the ETR d
Fuel Element Shipping Containers for the transport and storage of GETR
[
fuel elements from that facility to EG&G facilities at the Idaho National u
FEE EEMPT DOd 1378$
8-
'"O 001 79o8280
Mr. Charles E. MacDonald ggp g
Engineering Laboratory (INEL).
In order that the fuel be removeo,;,. the Vallecitos reactor by the end of August 1979, your expeditiaus review of this submittal is requested in order that the General Electric Co may r.
function as the shipper.
r-g G. E. Cunningham, Senior Licensing Engineer, at the Vallecitos Nuclear Center has requested that NRC approval be granted for the use of the ETR Fuel Element Shipping Container by that facility under the general license provisions of paragraph 10 CFR 71.12(b).
ID has listed the Vallecitos Nuclear Center as a " registered user" of the subject container and will forward them a copy of:
,7 1.
EG&G Idaho, Inc., Report No. PR-T-79-011, ATR Fuel Element Shipoini
~'
Container Safety Analysis, USA /5705/AF(ERDA-ID), Revision A (TR-466),
dated April 10, 1978.
2.
EGaG Idaho, Inc., Report No. PR-T-79-012, ETR Fuel Element Shipping Container Addendum to pR-T-79-011 (TR-466), dated August 7,1979.
In conclusion, we believe that as in the case of the ATR Fuel Element Shipping Container, the ETR Fuel Element Shipping Container fulfills the safety requirements contained in ERDA Manual Chapter 0529, 10 CFR Part 71, and 49 CFR Parts 100 - 199.
If you have any questions, please contact S. W. Farkas, Operational Safety Division, ID.
Very truly yours, M
/
Charles E. Williams Manager
Enclosures:
As stated (8) cc:
(w/oencl.)
D. M. Ross, DOE-HQ G. E. Cunningham, Vallecitos Nuclear Center i
137S8 v
'"O 002
For1n DOE-618 U.S. DEPARTMENT OF ENERGY iir.m CERTIFICATE OF COMPLIANCE
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Fo, Rad.oaci.vi uaieriais Pacmages ERDAM 5201 i.,
c..r i.e.mt e N omi,
ib Re.s.nn No.
iic Pacs age letentifictit.on No.
{ id. Page No.
le Toui No p,p USA /5705/AF(DOE-ID)
Rev. 1 IUSAL5705/AF(DOE-IDI 1
3 2 P'M Astat.E Th s cre f.f.c.iie.s essocd t a satisf y Sect.ons 173 393a,173 3) 3. t 73.395. and 173.19tiod the Ocoartrnent of Transportation Haiaracus Materia's Hivplai.ons (a9 CFR 170-189 and 14 CF R 103) and Sectons 146-19-104 and 146-19-100of the Departrnent of Transportation Can9erous Cargoes Reg 4ations (46 CFR 146-149),as amended.
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The packagmg and contents desCr rbed in item 5 below, me.rts the safety standards set ' orth n suenart C of Tate 10. Code of Federal Requ6.ia ons. Par t 71,"Packagmg of R.ideoact we Materias for Transport and Trans,ao, tat en of Radioactive Mate'-ai Under Certa.n Cond oons ~
h.
This ter tit.cate does not releeve the consignor from comphance wwsth any redluwerheet of the segulations of the U S. Department of le.insportaten or other Jpphcable rcujulatory agenc;es, including the government of any Country through or into whaCh the pieckage will be transported.
3 1 his arttetic. te.s.ssued on the basis of a wfety analysis report of the package design or accocation-(1) Pr enir eit by INJme and addressJ:
(2) T.tle and Idenerfication of report or apphcation:
(3) Dat e-EG&G Idaho, Inc.
Aerojet Nuclear Co.
As Noted P. O. Box 1625 Report No. TR-466, ATR Fuel Element Idaho Falls, Idaho 83401 Shioping Container Safety Analysis, June 30, 1975 EG&G Idaho, Inc.
Report No. PP-T-79-012, ETR Fuel Element Shippina Containers, Aug.
7, 1979 (Addendum to PR-T-79-Oll cN.ci T:oNs 4
[TR-466j)
Th s cert.f.cate.s cend.e.onal upon the f unfeii.ng of the requerernents of Suboort O of 1C CFR 71, as aogheabie, and the cond.tions spec:fied f
n *cito a 1 efoww S
D.m
,.t.on 04 P uh,* 309 and Authorized Contents, Mooel Number, F essite Class. Other Conditions, and Re'erences:
(a) Packagings (1) Models - tTR and ETR Fuel Element Shipping Containers (2) Descriptions ATR Fuel Element Shioning Container The inner container is a right parallelepiped 69-1/2 inches x 26-13/16 inches x 6-11/16 inches, constructed of 3/4-inch plywood, covered with 16-gage steel. The top and bottom are lined with high density polyethylene fcam with 0.020-inch cadmium plate. Wood spacers covered with sponge rubber and 0.020-inch cadmium plate provide separation for four fuel assemblies.
Positive closure is provided by a continuous hinge and two wire sealed hinge pins provide access.
The outer container is an overpack, 79 inches x 27 inches x 11 inches, constructed of 1-inch plywood, framed by steel angle members and covered with 18-gage steel. Aluminum, honeycomb impact limiters are fixed to the ends of the overpack.
Positive closure of the overpack is provided by four hinge pins which are secured in place using 1/16-inch diameter cotter pins.
The package weight is approximately 853 pounds when loaded.
August 1979 i *. E o.re on None c
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ER THE U.S. GEMR~ME:E UF ET;EWr m (ff NE Issuing Ofrice) u Signature,,iame, arc Ti-le (of :Cl i 70 RL Department of Enerqv (DOE)
Idaho Operations Office Ig/s/ [' Astrovin.c Of ficial) e i
/
c 550 Seccnd Street i F NY U 4 4'O " #,
@,f Charles E. Williams, Manager a
" O 003
Page 2 Certificate No. 5705 - Revision No. 1 (a) Packaging (Com inued)
(2) ETR Fuel Element Shipping Container The inner container is a right parallelepiped 56-3/4 inches x 16-1/2 incnes x 10-13/16 inches, constructed of 3/4 inch plywood, covered with 16-gage steel. The top and bottom are lined with 1/4 inch of high density polyethylene with 0.020-inch cadmium plate. The spacer separating the two layers of the three fuel assemblies consists of 1-inch high density polyethylene,1-inch of latex foam rubber, and 0.040-inch cadmium plate.
Positive closure is provided by a continuous hinge and two wire sealed hinge pins provide access.
The outer container is an overpack, 71 inches x 21-1/4 inches x 15-3/8 inches, constructed of 1-inch plywood, framed by steel angle members and covered with 18-gage steel. Aluminum impact limiters (3-1/2 inches) are fixed to the ends of the overpack.
Positive closure of the overpack is provided by four hinge pins which are secured in place using 1/16 inch diameter cotter pins. The package weight is approximately 690 pounds when loaded.
(3) Drawings ATR Fuel Eiement Shippino Container The packaging is fabricated in accordance with Idaho Nuclear Corporation Drawings Nos. 035927, Rev. B; 035928, Rev. C; 035929, Rev. C; 035932, Rev. A; and Phillips Petroleum Company Drawings Nos. ATR-E-1052, Rev. C. and ATR-E-1052, Rev. C.
ETR Fuel Element Shippino Container The packaging is fabricated in accordance with Idaho Nuclear Corporation ETR Drawing E-1012 - Rev. E 532-0642-47-400-021712.
(b) Contents (1) Type and Form of Material ATR Fuel Element Shipoina Container Solid, unirradiated material, as either clad rods or plates or fuel elements.
The concentration of the U-235 isotope shall not exceed 700 grams per linear foot in each of the four compartments.
ETR Fuel Element Shipping Container
~
Six (6) solid unirradiated material ETR or GETR fuel elements or control rod follower pieces (one in each compartment) provided they contain no more than 520 grams of U-235 per element or follower piece.
13788 NO 004
Page 3 Certificate N',. 5705 - Revision No.1 (b) Contents (Continued)
(2) Maximum quantity of material per package not to exceed Type A quantities.
ATR Fuel Element Shioping Container Total U-235 content not to exceed 12,000 grams per package.
ETR Fuel Element Shipping Container Total U-235 content not to exceed 3,120 grams per package.
(3) The contents shall be maintained within the respective element compart-ments and the active fuel lengths shall be completely within the regions of the cadmium covered spacers. Wood spacers may be used to accomplish this.
(4) Fissile Class I Applies to both ATR and ETR Fuel Element Shipping Containers.
(5) Chemical composition and form must not be reactive with the packaging, must not be explosive and must not have a hydrogen atom density, when averaged over the volume of the contents, greater than that of water at one gram per cubic centimeter.
(6) Heat generation shall not exceed 0.1 watt.
(7) Surface radiation level and transport index will be in accordance with 49 CFR Parts 170-189.
(c) References (1) Aerojet Nuclear Company Report ANCR-1100, Protective Shiocing Packaaes for Radioactive and Fissile Material, D. A. Tobias, et al, March 1968.
(2) Aerojet Nuclear Company Report No. TR-466, ATR Fuel Element Shiocing Container Safety Analysis, June 30, 1975.
NOTE:
This document was reissued as: EG&G Idaho, Inc., Report No.
PR-T-79-Oll (TR-466).
(3) EG&G Idaho, Inc., Report No. PR-T-79-012, ETR Fuel Element Shipoina Containers - Addend'um to PR-T-79-Oli (TR-466), August 7,1979.
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U.S. DEPARTMENT OF ENERGY IDAHO OPERATIONS OFFICE
SUMMARY
EVALUATION ETR FUEL ELEMENT SHIPPING CONTAINERS USA /5705/AF(DOE-ID)
AUGUST 1979 GENERAL The ETR Fuel Element Shipping Containers are part of the following family of shipping containers of similar design which have been issued Certificates of Canpliance:
DOE NRC 1.
ATR Fuel Element USA /5705/AF(DOE-ID)
USA /9099/AF Shipping Containers 2.
MTR Fuel Element (Not issued)
USA /5705/AF Shipping Containers This Summary Evaluation addresses those features unique to the ETR Fuel Element Shipping Container and should be considered an addendum to the Safety Evaluation for the ATR Fuel Element Shipping Container, USA /5705/AF(DOE-ID), October 1975.
DESCRIPTION The designs of the ATR-ETR-MTR Fuel Element Shipping Containers incorporate an inner steel-covered plywood container, with fuel element positioning compartments, within an overpack constructed of steel-covered plywood with aluminum honeycomb impact limiters on the ends.
TESTING The basic design of these containers was tested in 1968 and demonstrated the ability to successfully withstand the drop, fire, and impact tests required by ERDA Manual Chapter 0529 and 10 CFR 71.
The results of these tests are contained in Aerojet Nuclear Co. Report TR-466, ATR Fuel Element Shiopino Container Safety Analysis, dated June 30, 1975 [ subsequently reissued as EG&G Idaho, Inc., Report No. PP-T-79-Oll (TR-466), Revision A, same title, dated April 10,1978].
Therefore, all analyses performed for the ATR Fuel Element Shipping Containers apply to the ETR Fuel Element Shipping Containers.
The safety analysis for the ETR Fuel Element Shipping Containers is contained in EG&G Idaho, Inc., Report No. PP-T-79-012, ETR Fuel Element "O
006 13788
~
w Shipoing Containers - Addendum to PP-T-79-Oli (TR-466), dated August 7, 1979.
Those. sections of the analysis common to both ATR and ETR containers are not reiterated in the Addendum but are cross-referenced.
Therefore, the Addendum deals primarily with the description (size, weicht, con-struction, etc.), authorized contents, and criticality safen.
onsdierations of the ETR Fuel Element Shipping Containers.
AUTHORIZED CONTEN_TS The authorized contents permit the shipment of a maximum of six ETR or GETR fuel elements, arranged in two layers of three each divided by a polyethylene and cadmium separator.
The ETR and GETR fuel elements are exactly the same except for a slight difference in the end box of the ETR fuel element (the end box contains no uranium).
CRITICALITY
SUMMARY
Because the GETR fuel elements are near exact duplicates of the ETR fuel elements, no new criticality analyses were performed.
Instead, the analyses performed previously for the ETR fuel were reviewed by EG&G and DOE-ID criti:ality experts to confirm the validity of the previous work. Comparison of neutronically important parameters follows:
ETR Fuel GETR Fuel 5
V Loading per e!ement 500 grams 510 grams 235 Enrichment in U 93%
93%
Fuel Composition AIX U-Al alloy Remaining fuel element material Al Al Fuel Element Cross Section (mm) 76.2 x 76.2 77.7 x 76.2 Fuel Element Thickness (mm) 1.27 1.27 Number of Fuel Plates 19 19 Center to Center Fuel Plate
~
Spacing (mm) 3.94 - 4.29 4.06 Width of hater Void Between Plates 2.77 2.72 Fuel Meat Thickness (mm)
.508
.508 Fuel Meat Width (mm) 63 57 Fuel Meat Length (mm) 902 - 907 914
' N0 007 137ss
. Although small amounts of natural baron may be present in the ETR elements, no credit was taken for material in the analysis.
The ETR criticality analyses previously performed showed a Keff of s0.64 under normal conditions and a Keff of 0.975 for optimum water moderated conditions assuming an overloading of approximately 30%.
Two independent analysis used different calculational methods to arrive at similar conclusions.
The criticality analyses assumes that all or certaia parts of the cadmium poison remains intact within the shipping box. A thorough visual inspection was recently completed by EG&G Quality Assurance to verify physical condition of the boxes including the presence of cadnium sheets.
Furthermore three shipping containers were sampled at random with a neutron reduction measurement to verify the presence of a neutron absorber. All inspections were completed satisfactorily.
Based upon the above information, it is concluded that adequate provisions, analyses, and inspections have been made to assure criticality safety for all normal and credible abnormal events.
CONCLUSION Therefore, ID has concluded that based on an assessment of the tests performed on similarly-designed containers and the limitation of the authorized contents of ETR and GETR fuel elements contained in the Addendum (PP-T-79-012) the ETR Fuel Element Shipping Containers meet the requirements of ERDA Manua~ Chapter 0529 and 10 CFR 71.
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Stephen W. Farkas Health Physicist
"'O 008 13788
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fl. Bonicelli R. J. Fielding J. D. Ford C. J. Haire A. L. Kologi L. D. Kubicek D. R. Mouseau R. B. O'Brien H. R. Ome - 8 R. I. Pierce M. J. Schell D. S. Schoonen F. R. Vandewiele - 10 f t. S. Vargo Technical Library - 2 ACG Original
' "O 010 13788
FORWARD In July, 1979 EG&G Idaho, Inc. was requested to evaluate the ETD, Fuel Element Shipping Container for compliance with existing transport retulations, in order to ship GETR fuel elements from Vallecitos, California to the INEL.
Technical report PR-T-79-011 (TR-466), "ATR Fuel Element Shipping Container Safety Analysis," was used as a basis for this evaluation.
The safety analysis contained in technical report PR-T-79-Oli (TR-466) was performed utilizing the ATR, ETR, MTR, and SPERT shipping containers.
The report. determined the ETR Fuel Element Shipping Container does comply with the existing transport regulations for a Type A quantity, Fissile Class I shipping container.
The ETR and GETR fuel elements are essentially identical in physical size, construction, and fissile material content, the analysis documented in this repor t has determined the shipment of GETR fuel elements in the ETR shipping container to be safe and pose no threat to the public health and safety.
"O Oli
CONTENTS 0.0 General Infomation 0.1 Introduction 0.2 Package Description 0.3 Authorized Contents of Packaging 0.3.1 Fissile Material Limits 0.3.2 Radioactivity Limits See PR-T-79-Oll (TR-466) page 0-4 0.3.3 Physical and Chemical Form See PR-T-79-Oll (TR-466) page 0-4 0.3.4 Heat Generation See PR-79-Oll (TR-466) page 0-4 0.4 Administrative Controls See PR-T-79-011 (TR-466) page 0-4 1.0 Structural Evaluation See PR-T 1 (TR-466) page 1-1 1.1 Structural Design See PR-T-79-Oli (TR-466) page 1-1 1.2 Weights and Centers of Gravity 1.3 Codes and Standards See PR-T-79-011 (TR-466) page 1-2 1.3.1 Mechanical Properties See PR-T-79-Oll (TR-466) page 1-2 1.4 Compliance with General Standards for all Packaging See PR-T-79-011 (TR-466) page 1-2 1.4.1 Chemical and Galvanic Reactions See PR-T-79-011 (TR-466); page 1-3 1.4.2 Positive Closure See PR-T-79-Oll (TR-466) page 1-3 1.4.3 Lifting Devices See PR-T-79-Oll (TR-466) page 1-3 1.4.4 Tie Down Devices See PR-T-79-Oli (TR-466) page 1-3 1.5 Standards for Type B and Large Quantity Packaging See PR-T-79-Oll (TR-466) page 1-3 1.6 Compliance with Standards for Nor nal Conuitions of Transport See PR-T-79-Oli (TR-466) page 1-4
- 1. 6.1 Heat see PR-T-79-011 (TR-466) page 1-4 1.6.2 Cold see PR-T-79-Oll (TR-466) page 1-4 1.6.3 Pressure see PR-T-79-Oll (TR-466) page 1-4 1.6.4 Vibration see PR-T-79-Oll (TR-466) page 1-5 1.6.5 Water Spray see PR-T-79-Oll (TR-466) page 1-5 1.6.6 Free Drop see PR-T-79-011 (TR-466) page 1-5 1.6.7 Corner Drop see PR-T-79-011 (TR-466) page 1-6 1.6.8 Penetration see PR-T-79-Oli (TR-466) page 1-6 1.6.9 Compression see PR-T-79-011 (TR-466) page 1-7
~ "O 012 i
1-7 Compliance with Standards for Hypothetical Accident Conditions See PR-T-79-Oll (TR-466) page 1-8 1.7.1 Free Drop see PR-T-79-Oll (TR-466) page 1-9 1.7.2 Functure see PR-T-79-Oll (TR-466) page 1-10 1.7.3 Thermal see PR-T-79-011 (TR-466) page 1-16 1.7.4 Water Imersion see DR-T-79-011 (TR-466) page 1-16 1.7.5 Sumary and Conclusion see PR-T-79-011 (TR-466) page 1-18 l-8 Appendicies 1.8.1 Engineering Drawinc of ETR Shipping Box 1.
ETR Fuel Assembly Shipping Container Assembly and Detail.
1.8.2 Impact Calculations for Protective Container see PR-T-79-Oll (TR-466) page 1-25 1.8.3 Handle Lifting Calculations see PR-T-79-011 (TR-466) page 1-33 1.8.4 References see PR-T-79-Oll (TR-466) page 1-47 2.0 Thermal Evaluation see PR-T-79-011 (TR-466) page 2-1 2.1 Discussion see PR-T-79-Oll (TR-466) page 2-1 2.2 Summary of Thennal Properties of Materials see PR-T-79-Oli (TR-466) page 2-1 2.3 TechnicalSpecifidationsofComponents see PR-T-79-011 (TR-466) page 2-1 2.4 Thennal Evaluation for Nonnal Conditions of Transport see PR-T-79-Oll (TR-466).page 2-1 2.5 Hypothetical Thermal Accident evaluation see PR-T-79-Oll (TR-466) page 2-6 2.5.1 MTR Container see PR-T-79-Oll (TR-466) page 2-7 2.5.2 Analytical Methods see PR-T-79-Oli (TR-466) page 2-11 2.5.3 MTR Container with Outer Container see PR-T-79-011 (TR-466) page 2-12 2.5.4 ATR Container see PR-T-79-011 (TR-466) page 2-15 2.6 Appendix 2.6.1 Thermal Test on Polyethylene Sheet see PR-T-79-Oli (TR-466) page 2-19 3.0 Containment see PR-T-79-011 (TR-466) page 3-1 4.0 Shielding see PR-T-79-Oll (TR-466) page 4-1 M0 013 ii
5.0 Criticality Evaluation 5.1 Primary Criticality Analysis 5.2 Independent Criticality Analysis 6.0 Operating Procedures see PR-T-79-Oll (TR-466) page 6-1 6.1 Procedure For Loading see PR-T-79-Oll (TR-466) page 6-1 6.2 Procedure For Unloading see PR-T-79-Oll (TR-466) page 6-2 6.3 Preparation of Empty Package For Transport see PR-T-79-Oll (TR-466) page 6-3 7.0 Acceptance and Maintenance Program see PR-T-79-Oll (TR-466) page 7-1 7.1 Acceptance Tests see PR-T-79-011 (TR-466) page 7-1 7.2 Maintenarm Program see FR-T-79-011 (TR-466) page 7-1 7.3 Inspection / Maintenance Flan see PR-T-79-Oll (TR-466) page 7-2 7.3.1 Objective see PR-T-79-Oll (TR-466) page 7-2 7.3.2 Procedure see PR-T-79-Oli (TR-466) page 7-2 8.0 Quality Assurance see PR-T-79-Oli (TR-466) page 8-1 8.1 Determination of Intact Cadmium Sheets 8.2 ETR Fuel Element Container Cadmium Insoection with matron Source
" ^:0014 iii
0.0 General Information 0.1
==
Introduction:==
The ETR Fuel Element Shipping Containers are used for the transport of fuel elements for the Engineering Test Reactor (ETR) operated by EG&3 Idaho at the Idaho National Engineering Laboratory (INEL). The containers were analytically evaluated to determine their compliance with ERDA 0529 and 10CFR71 governing containers in which fissile materials are transported.
Those tests and evaluations are reported in USA /5705/AF (ERDA-ID) "ATR Fuel Element Shipping Containers Safety Analysis," Report No. PR-T-79-Oll (TR-466).
Those characteristics which are unique to the ETR container are discussed in this report. The results show that the ETR containers comply wi'.h the applicable regulations.
When fissile or radioactive materials are transported, the packaging and contents must meet standards specified in ERDA Manual Chapter 0529,
" Safety Standards for the Packaging of Fissile and Other Radioactive Materials,"
its Appendix and also Title 10, Part 71 of the Code of Federal Regulations, Packaging of Rad'oactive Material for Transport to assure protection of the public heal.a and safety.
These standards state the reouirements for criticality safety, structural integrity, thermal and shielding capabilities, quality assurance and maintenance and operating instructions. Any package used for the transport of fissile material must be shown to meet these standards, by test or computational methods, before issuance of a Certificate of Compliance. The tests and computational analysis of the ETR Fuel Element Shipping Container to detemine compliance with the above standards, as a Type A quantity, Fissile Class 1 container, are reported herein.
0.2 Package Description The ETR Fuel Elemen. Shipping Container is used for shipping new, unirradiated fuel elements from the supplier to the Engineering Test Reactor (ETR) at the Idaho National Engineering Laboratory (INEL).
Each container (Nos.1 through 23) is designed to transport, in a horizontal position 6 ETR fuel elements, in two layers of 3 alements.
Each fuel element contains approximately 500 grams of U-235.
The container as shown in figure 1, actually consists of two containers, one inside of the other.
The inner container, drawing ETR E-1012, is the container originally designed for the transportation of ETR fuel elements.
It is constructed mainly of 16 gauge steel covering 3/4-inch fire resistant, exterior plywood.
Cadmium sheets.020-inches thick are used for neutron absorption and are located above, below, and along both sides of the container.
In addition two sheets of cadmium are placed as a spacer between the two layers of fuel elements.
One-quarter inch polyethylene theets are located external to the upper and lower cadmium sheets for neutrcn moderation. Two sheets of 1/4-inch polyethylene and one sheet of 1/2-inch polvethylene are placed between the two cadmium sheets of the spacer, also for neutron moderation.
The lid is held shut by pinned steel hinges.
. 70 015
The external dimensions of tne
-,'ainer are 56.75 inches The cavity is 51.25 inches long by 16.5 inches wide by 10.8 i and contains a spacer long by 14.75 inches wide by 8.1 ir.
51.1 inches long by 14.75 inches wu
'nches high.
By using the spacer, 6 chlindrical compartment eve in the inner container for fuel elemencs or cont ol rod follt
_ieces.
The outer container was designed to enable the complete package to meet the requirements of E90A Appendix 0529.
It is constructed by using 18 gauge 3 teel-covered 1-inch extarior, fire resistant plywood, with a steel sheathed 3 1/2-;nch tFick aluminum honeycomb shock absorber at each end. The lid is secured to the body by four carbon steel hirges, the leaves of which are welded to the sides of the lid and body near the ends of the lid.
The external dimensions of the outer container are 71 inches long by 21.25 inches wide by 15.38 inches high. The cavity is 57 inches long by 17 inches wide by 11.4 inches high.
For lid lifting purposes there are four 20-inch, 60 sections of 4-inch, schedule 40 steel pipe welded to the lid of the outer container.
Each pipe section has three 0.19-inch gusset plates welded between the pipe section and lid section at even spaces.
Figura l shows the shipping container inside the outer container.
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0.3 Authorized Contents of, Packaging The authorized contents and limits are as follows:
0.3.1 Fissile Material Limits the ETR Fuel Element Shipping Containers are authorized for Fissile Class 1 transport with the following limits:
(a) One ETR or GETR fuel element or one ETR or GETR control rod follower piece may be loaded into each of the six compartments, provided that they contain no more than 520 nrams of U-235 per element or follower piece.
(b) The uranium must be contained to the longitudinal region of the container ctotaining cadmium.
The physical dimensions between the ETR and GETR fuel elements are the same. The only difference is the end box of the ETR fuel element is slightly more pointed. The erd box contains no uranium.
0.3.2 Radioactivity Limits Refer to P-T-79-011 (TR-466) page 0-4 0.3.3 Physical and Chemical Form Refer to PR-T-79-011 (TR-466) page 0-4 0.3.4 Heat Generation Refer to PR-T-79-011 (TR-466) page 0-4 0.4 Administrative Controls Refer to PR-T-79-011 (TR-466) page 0-4 1.0 Structural Evaluation Refer to PR-T-79-011 (TR-466) page 1-1 i.1 Siructural Design Refer to PR-T-79-Oli (TR-466) page 1-1 1.2 Weights and Centers of, Gravity The total calculated shipping weight (including fuel element) of the ETR container is 690 pounds.
The weight of the contents for fissile shipments other than ETR fuel elements, is unknown. However, the space available for the contents is sufficiently small that gross weight variations will not be large enough to invalidate the stress analysis.
The center of gravity is essentially the geometric center of the container, excluding skids.
o'O O18. _ _ - -..
1.3 Codes and Standards Refer to PR-T-79-Oll (TR-466) page 1-2 1.3.1 Mechanical Properties Refer to PR-T-79-Oll (TR-466) page 1-C 1.4 Compliance with General Standards for all Packacino 1.4.1 Chemical and Galvanic Reactions Refer to PR-T-79-011 (TR-466) page 1-3 1.4.2 Positive Closure Refer to PP.-T-79-Oll (TR-466) page 1-3 1.4.3 Lifting Devices Refer to PR-T-79-Oli (TR-466) page 1-3 1.4.4 Tie Down Devices Refer to PR-T-79-Oll (TR-466) page 1-3 1.5 Standards for Type B and Large Quantity Packaging Refer to PR-T-79-Oll (TR-466) aage 1-3 1.6 Compliance with Standards for Normal Ccnditions of_ Transport Refer to PR-T-79-Oll (TR-466) page 1-4
- 1. 6.1 Heat Refer to PR-T-79-Oll (TR-466) page 1-4 1.6.2 Cold Refer to PR-T-79-Oll (TR-466) page 1-4 1.6.3 Pressure Refer to PR-T-79-011 (TR-466) page 1-4 1.6.4 Vibration Refer to PR-T-79-Oll (TR-466) page 1-5 1.6.5 Water Spray Refer to PR-T-79-Oli (TR-466) page 1-5 ^20 019
1.6.6 Free Drop Refer to PR-T-79-011 (TR-466) page 1-5 1.6.7 Corner Drop Refer to PR-T-79-011 (TR-466) page 1-6 1.6.8 Penetration Refer to PR-T-79-011 (TR-466) page 1-6 1.6.9 Compression Refer to PR-T-79-011 (TR-466) page 1-7 1.7 Compliance with Standards for Hyoothetical Accident Conditions g Transport Refer to PR-T-79-011 (TR-466) page 1-8 1.7.1 Free Droo Refer to PR-T-79-011 (TR-466) page 1-9 1.7.2 Puncture Refer to PR-T-79-011 (TR-466) page 1-10 1.7.3 Thennal Refer to PR-T-79-011 (TR-466) page 1-16 1.7.4 Water Imersion Refer to PR-T-79-011 (TR-466) page 1-16 1.7.5 Sumary_ and Conclusion Refer to PR-T-79-Oll (TR-466) page 1-18 "'0 020
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1.8.2 ImoactCalculationsforPNtectiveContainer Refer to PR-T-79-Oll'(TR-466) page 1-25 1.8.3 Handle liftino Calculations Refer to PR-T-79-011 (TR-466) page 1-33 l.8.4 References Refer to PR-T-79-011 (TR-456) page 1-47 2.0 Thermal Evaluation Refer to PR-T-79-011 (T-466) page 2-1 4
2.1 Discussion Refer to PR-T-79-011 (TR-466) page 2-1 2.2 Summary o_f_ Themal Procerties of_ Materials f
Refer to PR-T-79-011 (TR-466) page 2-1 2.3 Technical Specifications g Comconents Refer to PR-T-79-011 (TR-466) page 2-1 2.4 Then11a1 Evaluation for Nomal Conditions of, Transport Refer to PR-T-79-011 (TR-466) page 2-1 2.5 Hyoothetical Thermal Accident Evaluation Refer to PR-T-79-011 (TR-466) page 2-6 2.5.1 MTR Container Refer to PR-T-79-011 (TR-466) page 2-7 2.5.2 Analytical Methods Refer to PR-T-79-Oli (TR-466) page 2-11 2.5.3 MTR Container with Outer Container Refer to PR-T-79-Oll (TR-466) page 2-12 2.5.4 ATR Container Refer to PR-T-79-011 (TR-466) page 2-15 2.6 Appendix 2.6.1 Thermal Test o,n Polyethelene Sheet Refer to PR-T-79-Oll (TR-466) page 2-19 m70 023 3.0 Containment Refer to PR-T-79-Oll (TR-466) page 3-1 4.0 Shielding Refer to Pr-T-79-Oll (TR-466) page 4-1 5.0 Criticality Evaluation 5.1 Primary Criticality Analysis In order to rule out criticality of dry arrays of the ETR containers, a density analog calculation was run.
The results, with conservative parameters, indicated that it would require over one million elements for criticality. Thus the only plausible conditions under which criticality could occur would be that of flooding without intact cadmium plates.
There would have to be complete submergence in order to fill up the most important spaces, i.e. that between the fuel plates.
The paranount requirement for the containers is that none of the cadmium be melted out.
One calculation was made utilizing the ETR container with both the top and bottom layers of cadmium melted leaving only the cadmium plates between the bottom and top layers of fuel rods. Th Keff with 678 grams per element ETR fuel was 1.06 and dropped to.975 when the fuel loading was dropped to 500 grams per element. The criticality of the ETR containers has been analyzed assuming flooded conditions and with the cadmium :.1 tact.
The Keff for an infinite array of heavily loaded fuel (456 gm per foot) was 0.877. An additional calculation was made on the modified container with of.64.y) fuel separation and using the same loading.
This gave a Keff the add It can be seen that since the hypothetical accident will not adversly affect the structural integrity of the container, an infinite array of containers subjected to the accident and loaded with authorized contents listed in Section 0.3 using the administrative controls listed in 0.4 will remain suberitical with optimum moderation.
5.2 Independent Criticality Analysis Independent criticality calculations on the ETR Fuel Element Shipping April 301968, (gported by J. K. Fox in a letter to Dr. F. H. Tingey Containers were and are stated in this report.
I CI-1086, Protective Shiocing Packages for Radioactive and Fissile Material Containers, by D. A. Tobias, etal,1968, pg 10.
^: 0 02 4
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The calculational model was a conservative approximation of the actual shipping container.
The containers were modeled to be in an infinite array in the x and y dimensions, with the length (z dimension) of each box and the fuel element therein, being infinitely long.
Fissile material loading was the same as that used in the primary criticality-analysis, that is, 456 grams of U-235 per fcot. The fuel elements in the container were modeled with a separation of 50m (2 in).
Two cal-culations were performed.
In one case all open spaces in the model were filled with water.
In the second case only the ETR element itself contained any water in its interstitial spaces.
The calculations were perfomed with the PDQ code using four-group PHROG and TEMPEST generated cross sections. Values of Keff for the two types of calculations were 0.69 and 0.66 respectively.
These calculations were originally reviewed by the Nuclear Safety Comittee in 1968. An independent review by EG&G Safety Division was conducted in June 1979 on both the primary and secondary criticality analysis reported herein. Their conclusion was that the original analysis was valid and that an infinite array of containers subjected to the hypothetical accident will remain subcritical with optimum moderation.
6.0 Operating Procedures Refer to PR-T-79-Oll (TR-466) page 6-1 6.1 Procedure for Loading Refer to PR-T-79-Oll (TR-466) page 6-1 6.2 Procedure for Unloading Refer to PR-T-79-011 (TR-466) page 6-1 6.3 Preparation of_ Empty Package for Transoort Refer to PR-T-79-Oll (TR-466) page 6-3 7.0 Acceptance and Maintenance Program Refer to PR-T-79-011 (TR-466) page 7-1 7.1 Acceptance Tests Refer to PR-T-79-Oll (TR-466) page 7-1 7.2 Maintenance Program Refer to PR-T-79-Oll (TR-466) page 7-1 (2) J. K. Fox letter to Dr. F. H. Tingey, JKF-6-68, " Criticality Considerations of the New Shipping Container, April 30, 1968.
70 025 7.3 Inspection / Maintenance Refer to PR-T-79-Oll (TR-466) page 7-1 7.3.1 Objective Refer to PR-T-79-Oli (TR-466) page 7-2 7.3.2 Procedure Refer to PR-T-79-Oli (TR-466) page 7-2 8.0 Quality Assurance Refer to PR-T-79-Oll (TR-466) page 8-1 8.1 Determination of Intact Cadmium Sheets EGaG. Quality Division made a visual inspection of all ETR Fuel Element Shipping 02ntainers in July 1979 to determine whether or not the cadmium sheets were intact. All sheets were in place in accordance with applicable drawings.
In addition, a random selection of three containers were subjected to inspection using a 5 curie neutron source and an Eberline neutron detector to check for presence of cadmium. As can be seen in Appendix 8.2, ETR Fuel Element Shipping Container Cadmium Inspection with Neutron Source, all cadmium sheets are in place and intact in accordance with applicable drawings.
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8.2 ETR Fuel Element Shipping Container Cadmium Inspectior; with Neutron Source
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s INTEROFFICE CORRESPONDENCE July 25, 1979 u.
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1, 9, and 19 were checked for cadmium on July 19, 1979. Mcck-ups of the containers were made with and without cadmium. Materials used for the mock-ups and all measurements were observed by L. V. Wages and I. E. Stepan.
Readings were taken using a 5 curie 9u Be source and a calibrated Eberline Instrument Corporation, MODEL NC-1 Serial No.101, neutron detector.
All measurements were done in accordance with drawings of the containers and all of the data which is attached would indicate cadmium being present as per drawings.
Attachment As Stated cc:
L. V. Wages (w/ attachments)
Central File D. M. Anderson Let*er File
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REFERENCES (1)
CI-1086, Protective Shicaing Packages for Radioactive and Fissile Material Containers, by D. A. Tobias, March 1968.
(2)
PR-T-79-011 (TR-466), ATR Fuel Element Shiocing Container Safety Analysis, by C. E. Friedrich and D. R. Swope, June 1975.
(3)
J. K. Fox letter to Dr. F. H. Tingey, JKF-6-68, " Criticality Considerations of the New Shipping Container, April 30, 1968.
(4)
D. M. Anderson letter to D.
.4csworth, DMA-4-79, "ETR Fuel Element Shipping Containers," July 25, 1979.
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