ML19221B297
| ML19221B297 | |
| Person / Time | |
|---|---|
| Issue date: | 03/29/1979 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| References | |
| REGGD-07.009, REGGD-7.009, NUDOCS 7903300556 | |
| Download: ML19221B297 (36) | |
Text
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1..
OFFICE OF STAND ARDS DEVELOPMENT REGULATORY GUIDE 7.9 STANDARD FORMAT AND CONTENT OF PART 71 APPLICATIONS FOR APPROVAL OF PACKAGING OF TYPE B, LARGE QUANTITY, AND FISSILE RADI0 ACTIVE MATEPsIAL USNRC REGULATORY GUICES
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TABLE OF CONTFN15 Page INTRODUCTION.
i Purpose of Standard Format.
i Applicability of Standard Format.
ii Use of Standard F ormat.
ii Style and Composition.
ii Rtvisions.
iii Physical Spacifications.
iv 1.
GENERAL INFORMAIl0N.
1-1 1.1 Introduction.
1-1
- 1. 2 Package Description.
1-1 1.2.1 Packaging.
1-1 1.2.2 Operational features.
1-1 1.2.3 Contents of Packaging.
1-1
- 1. 3 Appendix.
1-2 2.
STRUCTURAL EVALUATION.
2-1 2.1 St ructural Des ign.
2-1 2.1.1 Discussion.
2-1 2.1.2 Design Criteria.
2-1 2.2 Weights and Centers of Gravity.
2-1 9
2.3 Mechanical Properties of Materials.
2-1 2.4 General Standards for All Packages.
2-2 2.4.1 Chemical and Galvanic Reactions.
2-2 2.4.2 Positise Closure.
2-2 2.4.3 Lifting Cesices.
2-2 2.4.4 Tiedown De/ ices.
2-2 2.5 Standards for Type B and Large Quantity Packaging.
2-2 2.5.1 Load Resistance.
2-3 2.5.2 External Pressure.
2-3
- 2. 6 Normal Conditions of Iransport.
2-3
- 2. 6.1 Heat.
2-3
?.6.2 Cold.
2-3 2.6.3 Pressure.
2-4 2.6.4 Vibration.
2-4 2.6.5 Water Spray.
2-4 2.6.6 Free Drop.
2-4 2.6.7 Corner Drop.
2-4 2.6.8 Penetration.
2-4 2.6.9 Compression.
2-4
- 2. 7 Hypothetical Accident Conditions.
2-4
- 2. 7.1 Free Drop.
2-5
- 2. /. 2 Puncture.
2-7
- 2. 7. 3 Thermal.
2-/
- 2. 7. 4 Water Immersion.
2-/
- 2. /. 5 Summary of Damage.
2-/
TABLE OF CONTENTS (Cont'd) till 2.8 Special form.
2-7 2.8.1 Description.
2-8 2.8.2 F ree Drop.
2-8 2.8.3 Percussion.
2-8 2.8.4 Heating.
2-8 2.8.5 Immersion.
2-8 2.8.6 Summary.
2-8
- 2. 9 fuel Rods.
2-8 2.10 AppenJix.
2-8 3.
THERMAL EVALUATION.
3-1 3.1 Liscussion.
3-1
- 3. 2 Summary o f Thermal Properties of Materials.
3-1 3.3 Technical Specif ications of Components.
3-1 3.4 Thermai Evaluation for Normal Conditions of Transport.
3-1 3.4.1 Thermal Model.
3-1 3.4.2 Maximum Temperatures.
3-2 3.4.3 Minimum Temperatures.
3-2 3.4.4 Maximum Internal Pressures.
3-2 3.4.5 Matimum Thermal Stresses.
3-2 3.4.6 Evaluation of Package Performance for Normal Conditions of Transport.
3-2
- 3. 5 Hypothetical Accident Thermal Evaluation.
3-2 3.5.1 Thernal Model.
3-3 3.5.2 Package Conditions and Environment.
3-3 3.5.3 Package Temperatures.
3-3 3.5.4 Maximum Internal Pressures.
3-3 3.5.5 Maximum Thermal Stresses.
3-4 3.5.6 Evaluation of Pack age Perf ortunce for the Hypotheticai Accident Thermal Conditions.
3-4
- 3. 6 Appendix.
3-4 4.
CCNTAIhMENT.
4-1 4.1 Contairment Bound 3ry.
4-1 4.1.1 Containmont Vessel.
4-1 4.1.2 Containment Penetrations.
4-1 4.1.3 Seals and Welds 4-1 4.1. 4 Closure.
4-1 4.2 Requirements for Normal Conditions of Transport.
4-]
4.2.1 Release of Radioactive Material.
4-1 4.2.2 Pressurization of Containment Vessel.
4-1 4.2.3 Coolant Contamination.
4-2 4.2.4 Coolant Loss.
4-2 4.3 Containment Requirements for the Hypothetical Accident Conditions.
4-2 4.3.1 Fission Gas Products.
4-2 4.3.2 Releases of Contents.
4-2 4.4 Appendix.
4-2 5.
SHIELDING EVALUATION.
5-1 5.1 Discussion and Results.
5-1
- 5. 2 Source Specification.
5-1
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TABLE OF CONTENTS (Cont'd)
I.d.f 5.2 1 Gamma Source.
5-1 5.2.2 Neutron Source.
5-1 5-1
- 5. 3 Model Specification.
- 5. 3.1 Description of the Radial and Axial Shieloing Configuration.
5-1 5.3.2 Shield Regional Densities.
5-2 5-2 5.4 Shielding Evaluation.
5-2
- 5. 5 Appendix.
6.
CRITICALITY EVALUATION.
6-1 6.1 Discussion and Results 0-1 6-1 6.2 Package Fuel Loading.
6-1
- 6. 3 Model Specification.
6.3.1 Description of Caiculational Model.
t-I 6.3.2 Package Regional Densities.
6-1 6-1 6.4 Criticality Calculation.
6.4.1 Calculational or Eg erimental Methnd.
6+
6-4 6.4.2 f uel Loading or Other Contents Loading Optimization.
6-4 6.4.3 Criticality Results 6.5 Critical Benchmark Emperiments.
b-4 8
6.5.1 Benchmark Experiments and Applicability.
6-4 6.5.2 Details of the Benchmark Calculations.
6-5 6.5.3 Results of the Conchmark Calculations.
6-5 e-5 6.6 Appendi=
7.
OPE RAllNG PROCEDURES.
/- 1
/.1 Prncedures for loading the Package.
/- 1
- 7. 2 Procedures for Unloading the P'.ckage.
/-l
- l. 3 Preparation of an Empty Package for Transport.
/- 1 7-1
- 1. 4 Appendix.
S.
ACCEPTANCE TE ST S AND MAINTENANCE PF0 GRAM.
8-1 8.1 Acceptance Tests.
t-1 8.1.1 Visual Inspection.
M-1 8.1.2 5tructural and Pressure Tests 8-1 8.1. 3 Leak Tests.
M-1 8.
4 Component Tests.
M-1 8.1. 5 Tests for Shielding Integrity.
A-2 8.1. 6 Thermal Acceptance Tests.
8-2 "2
- 8. 2 Maintenance Program.
S. 2.1 Structural and Pressure Tests.
x-3 8 2.2 Leak Tests.
8-3 B-3 8.2.3 Subsystems Mainten3nce.
8.2.4 Valves, Rupture Discs, and Gaskots on Containmont vessel.
8-3 8.2.5 Shielding.
8-3 8.2.6 Thermal.
8-3 9
- 8. 7. 7 Miscellaneous.
A-3 144 138
D IN'WCDUCIICN This regulatory guide has been compiled by the United 5tates Nuclear Regulatory Commission (NRC) as an aid in the preparation of applications for approval of packaging to t;e used for the shipment of type B, lirge quintity, and fissile ralicactive material.
It is not inteoded as an interpretatico of Commission regulations, w; thin the meaning of NN 30.5, 40.6, /0. 6, or /1.14, Parts 30, 40, /0, or /1, respectively, of Title 10 of the Code of Federal Regulations. Nothing n this guide miy be construed as having the force and ef f ec t of NRC regulations, nor "ontained i
.i s indicating that applications supported by safety analyses and prepared in accordante with the recommenditions ut this regulatory guide neces>arily will be approved, nor as relieving any licensee from the requirements of 10 C f R Parts 30, 40, /0, and /1,* and any other pa tinent regulations.
This regulatory guide should not be considered a substitute for r ef erence to 10 Cf R Fart /1,
" Packaging of Radioactive Miterial f or Transpurt and Transportation of Radioactive Miterial Under Certain Conditions." Its primary purpose is to assist t he app l ic. int in prepiring an application that thoroughly and ccmpletely demonstrates the adequacy of the picago in meeting the reg'lations.
In addition to an approval of packaging, the applicant mast have an approved quality assurance program in accordince with the provisions of 6 /1.51 of 10 CFR.
Additional information will be requested in support of an applic ation if NRC believe3 that such information is necessary to provide reasonable assurant> of the safety of the proposed shiament. In preparing an applica-tion for approsil of packiqing, the applicant may find it useful to refer to other regulatory guides of Division /, "Iransportation."
Inquiries about these regulatory gaides may t:e directed to the U.S. Nuclear Regulatory Commission, ushington, D.C. N555, Attention: Director, Division of Technical Inf ormation and Document Control.
Purpose of Standard format The purpose of the Standard Format an't Content of Part /l Applications for Approval of Packaging of Type B, large Quantity, and fissile Radio.ictive Material (hereinitter "Stanlird Format") is to indicate the information to be provided in the application and to establish a uniform format for presenting the information. Use of this formit will help ensure the conple-teness of the inf urmation provided, will assist the NRC staf f and others in locating the informa-tion,.ind w i l l aid in thortening the time needed for the review process.
The applic.ition is the principal document in which the applicint provides the information and tmises for the NRC staf f to det ermine whether or not the,'ickage meets t% requirements of 10 Cf R Part /1.
r The NRC staff is currently revising 10 CF R Part 71 to incorporate the IAEA-19/3 revisions.
Since the tommission has not approved publication of a proposed rule, this format guide does not attempt to incorporate possible chan es to Part /1.
As Part /1 is revised, this format quide wil l t'e appropriately modi f ied.
1/4 139 t
i
Applicability of Standard format This Standard format applies specifically to applications for approval of packaging of type B, large quantity, and f issile radioactive material under 10 CF R Part 71.
The Standard Format identifies general and detailed information required and will help ensure the comple-teness of the inf ormation provided.
Use of Standard F ormat The Standard Format presents a format for applications for approval that is acceptable to the NRC staff. Conformance with the St>ndard format, however, is not required. Applica-tions for approval with different formats will be acceptable *o the staff if they provide an adequate basis for the findings requisite to the approval of packaging. However, because it may be more difficult to locate needed information, the staff review time for such applica'. ions may be longer.
Upon r ceipt of an application, the NRC staff will perform a preliminary review to deter-mine if the application provides a reasonably complete presentation of the information that is needed to f orm a basis f or the f indings required bef ore approval of a package.a accordance with 10 CF R Part 71.
The Standard Format will be used by the staff as a q ideline to identifv tho a
type of information needed. If the application does not provide a reasonably complete presenta-tion of the necessary information, further review of the application will not be ~nitiated until a reasonably complete presentation is provided.
The information provided in the application should be up to d3te with respect to the state of technology for transportation of radioacti.e materials and should take into account recent changes in NRC regulations and guides, i nd.. ; t ry codes and standards, results of recent developments in transportation safety, and esperience in the construction and use of radioactive material packaging.
Style and Composition The applicant should strive for clear, conciso presentations of the information provided in the a plication. Confusing or amb;quous statements and unnecess arily vert]ose descripticos da not contrit ute to expeditious technical review.
Claims of adequacy 0+
designs or design methods shmald t;e supported by technical bases, i.e.
by an appropriate en.pteering evaluation er description of actual tests.
I e r n,s as defined in tha packaging and transport regulations must be used.
The application should follow the numbering system and headings of the Standard F orot at least to the heading 3 with three digits, e. g.
- 2. 4. 2 Pos i t i ve Closure. When a particular ree ire-ment does not apply to a package, the corresponding stbsection shool<' not Le omitted but aJdressed with t t'e term "Not Appl icab le. ' A reason should te offered for not addressing a particular requirement when there is doubt as to its applicability.
Appendices to each chapter of the application should include detailed information omitted f rom tha main text for clarity. A list of reports or other docunents that are ref erenced in the text of the application should be included in the appendix at the end of t e ct apte i hich m
they are referenced. When spetCfic,tems are referenced, page numbers should be provided. In cases where proprietary documents are referenced, a nonproprietary summary description of the document should also be ref erenced.
All physical tests of components and packages should be supported by photographs in the appendices of the appropriate chapter. Appendices to the application may also be used to provide supplemental information not explicitly identified in the Standard fermat.
Examples uf such inf ormation are (1) summaries of the manner in which the applicant has treated matters addressed in NRC regulatory guides e nd (2) supplementary information regarding calculational methods or design approaches used by the applicant or its agents.
Where numerical values are stated, the number of significant figures given should reflect the accuracy or precision to which the number is knoan.
bhere pnssibld, estimated limits of error or uncertainty should be given. Significant figures should not be dropped or rounded off if, by doing so, subsequent conclusions are inadequately supported.
Abbreviations should be consistent tnroughout the application ar;d should be consistent with generally accepted usage. Any abbreviations, symbols, or special terms unique to the prcposed packaging or not in general usage should be defined in each chapter of the application where they are used.
Drawings diagrams, sketcnes, and charts should be used where the information can be 9
presented more adequately or conveniently by such means.
Due concern should be taken to ensure that all information presented in drawings is legible, symbols are defined, and drawings are not reduced to the extent that visual aids are necessaiy to interpret pertinent items of informa-tion presented in the drawings.
Revisions Data and text should be updated or revised by replacirg pages. " Pen and ink" or " cut and paste" changes should not be used The changed or revised portion on each page should be highlighted by a " change indicator" mark consisting af a bold vertical line drawn in the margin upposite the binding margin. The line should be the same length as the cortion actu311y changed.
All pages submitted to update, revise, or add pages to the report should show the date of change and a change or amendment number.
A transmittal letter, including a guide page listing the pages to be inserted and the pages to be removed, should acccmpany the revised pages. Where applicable, supplemental pages may f ollow the revised page.
All statements on a revised page should be accurate as of the date of the submittals.
Special care should be taken to ensure that the main sections of the report are revised to 9
reflect any design changes reported in supplemental information, i.e.,
responses to NRC staff requests for information or responses to regulatory positions.
iii
Physical Specifications All material submitted as part of the application should conform to specific standards as to the physical dimensians of page size, quality of paper and inks, and numbering of pages, ex hibi ts, and attachments. More specifically:
1.
paper Size (not to exceed)
Text pages: 8-1/2 x 11 inches.
Drawings and graphics: 3-1/2 x 11 inches pref erred; however a larger size is acceptable provided:
a.
After reduction, the size does not exceed 11 x 17 inches, including a 2-inch margin at lef t f or binding.
b.
The f inished copy when f olded does not exceed 8-1/2 x 11 inches.
All drawings should have a dr,1 wing numDer, resision number, company nime, title, dite of rev i sion, and sheet number.
2.
P iper S toc k f
Weight or substance: 20 pound f or printinq on b)th sides 16 to 20 pound f or printin g on one side only.
Composition: Wood chemical sulphite (ro grcund-cod) and a pH of 5.5.
Color: 'nhite is pref erred, t;ut pastel colors are acceptable provided the ccMinat ion of paper s toc k and ink. is suitable for microfilmirg.
3.
Ink Color suf'ic iently dense to record on microf ilm or imige-copying equipment.
4.
Pale Margins A mirgin of no less th.in one inch should be maintained on the top, bottom, and t;inding side of al l p iges.
5.
Pr i n t i r3 Composition: iext nages should be single spaced.
i>pe f ont and style: Must be suit able f or microfilming.
Reproduction: May be mechanically or photographically reproduced. Text pages should nreferably be printed on two sides with the image printed f*ad to head.
O.
iv
6.
B i ni1 i rg Parjes should be punched f ur standird 3-hole looseleaf binder and contained within a binder supplied t,y the applicant.
/.
Pay Nebering Pages should be numbered by chapter and sequentially within the thipter.
8.
Separators Separators should be provided bet een each chapter of the application.
9.
Number of Copies Ten copies of the application should be provided.
9 wm 9
V
B 1
GFNERAL INFORMATION This chapter of the application should present an introduction and general package description.
1.1 Introduction This section should include the proposed use of the package, the model number, and, in the case of lissile packages, the proposed fissile class or classes, and the numt:er of p3ckages per shipment or transport index, as appropriate.
1.2 Package Description 1.2.1 Packaging The packaging description should include the gross weight, materials of construction, materials used as neut ron absorbers or moderators, external dimensions and cavity size, inteinal and enternal structures, receptacles, valves, sampling ports, mans of heat dissipation, volumes and types of coolant, outer and inner protrusions, lif ting and tiedown devices, amount of shield-ing, pressure relief systems, closures, and means of containment. The containment vessel should 9
t>e clearly identif ied.
Overall and cutaw3y sketches (8-1/2 x 11 inches) of the package should be included as part of the description, Drawings that clearly summarize the safety features considered in the analysis should be included in Appendix 1.3, e.g.,
material lists, dimensions, valves, g ekets, and weld specifica-tions should be included on the drawings. Detailed construction drawings of large, complex packages should not be included.
- 1. 2. 2 Op rational Features in the case of a complex package system, a discussion of the operation of the p a c k,i ge should be provided.
This would include a schematic diagram showing all valves, connections, pip ing, openings, seal s, conta inment boundaries, etc.
- 1. 2. 3 Contents of Packaging State the quantity of radionuclides (in the case of irradiated fuel shipments, also estim)te the quantity of radionuclides available for immediate release within the void space of the fuel rods), chemical and physical f orm, material density, moderator ratios, contiqurations as required for nuclear safety evaluation, the maximum amount of decay heat, maximum pressure buildup in the inner conta.iner, and any other loading restrictions.
1-1
- 1. 3 3-p e n d i a.
This appendix should i nc i t.Je detailed i n f e r r..i t i on describing the packvging. q e r i t i c o..i l f r atur es,
'rui contents of the pack 1: iJ ng such as dimensional drc# wings, di t.ii led o;.er a t i ona l sc r.4 mat ic s, ind loading conf igurat ions.
3a4 1A5 1-2
2.
STRUCTURAL EVALUATION This chapter of the application should identify, describe, discuss, and analyze the principal structural e,qineering design of the packaging, components, and systems important to saf ety and to compl: ' e with the perf ormance requirements of 10 CF L Part /1.
2.1 Structural Cesign 2.1.1 Discussio-Identify sne principal structural members and systems such as the containment vessel, impact limiters, closure devices, and valve ( that are vital to saf e operation of the package. Reference the location of these items on drawi,qs, and discuss their structural design and perf ormance.
2.1.2 Design Criteria Desc rit;e the load combinations and f actors that serve as design criteria. Design criteria may t'e used if judged acceptable by the NRC staff in meeting the structural requirements of H /1. 35 and /1. 3f> o f 10 CF R Part 71.
F or each of these criteria, state the maximum allowable stresses and strains (as a per centage of the yield or ultimate values) for ductile failure; describe how the other structural failure modes (e.g.
Drittle fracture, f atique, buckling) are 9
considered.
If different design criteria are to be al owed in various parts of the packaging or f or dif f erent conditions, the appropriate values fc each case should be indicated. Include the criteria that will be used for impact evaluation.
Identify all Codes and standards that are used to determine material properties, design limits, or methods cf comt ining loads and stresses.
In cases of deviation from standird codes, or if certain components are not covered by such codes, provide a de. ailed description of the design criteria used as substitutes.
2.2 Weights and Centers of Gravity L ist the total weight of the packaging and contents. Tabulate the weights of major individual subassemblies such that the sum of the parts equals the total of the package. Locate the center of grav i ty of the package and any other centers of gravity ref erred to in the application. It is not necessary to include the calculations made to determine these values, but a sketch or drawing that clearly shows the individual subassembly referred to and the reference point for locating its center of gravity should be included.
2.3 Mechanical Properties of Materials List all the material mechanical properties used i.' the structural evaluation. This miy include yield stress, ultimate stress, modulus of elasticity, ultimate strain, Poisson's ratio, density, and coefficient of thernal expansion. If impact limiters are used, include either a 8
compressian stress strain curve for the material or the force-deformation relationship for the limiter, as appropriate. For materials that are subjected to dynamic loadings or elevated 144 146 2-1
t empe r d u re s, the ipp%pri 3te mechanic al propert ies under these conditions should be specified to the estent used in the struc tural evaluation.
The source of all information in this section should be clairly and specifically referenced as to publicat ion and page number. 'nhere ma t er ia l properties are determined by testing, the test procedure, cond i t i ons, ar.d c+ as urement s shouid be described in suf ficient detail to allow the staf f to conclude th3t the results are valid.
2.4 General Standirds for All Packages This sec tion should state that the general stand ards f or all p ic k sqirs, speci f ied in t,
71.31, ar e complied wit h, a n demonstrated in tl.e f ollo.ing p iragraphs.
2.4.1 Chemic31 and Galsanic Ree tions Discuss possible chemical, yilvanic, er other reactions in the packaging or between tte p.a c k a g i n g and the package contents.
For each component material of the packaging, list all chemically or galvanically dissimilar materials with which it has contact.
Indicate any specific measures that have been taken to prevent contact or reiction between materials, and disc ss the ef f ect iveness of s uc h 1.ea sures.
2.4.2 Positive Closure De sc ribo and discuss th9 package closure systen, in suf f icient detail to shun that it cannot be inadvertently opened.
This demonstration snould include covers, i.ilves, or any other access that must be closed caring narcal t ran>por t stion.
'.43 titting Devices Identity.ill devices and attachments that can be used to lif t the package or its lid.
Show by testing or analysis that these devices comply wit h the requirements of S ll. 31(c) of 10 CFR Part 71.
Proside orawings or sketches that show the location and construction of these items.
Determina the effects of the forces imposed by lifting un vital package components, including the interfaces between the li f t ing device and other packaging surfaces. Documented vaiues of the yield stresses of the materials should be used as the criteria to demonstrate compliance w i th 9 71. 31(c ).
Tiedowa Devices i
2.4.4 Identify all devices that are a structural part of tr'e package and can be used as tiedowns.
Discuss the overall tiedown system. Show by testirq or analysis that these devices comply with the requiraments of 9 71.31(d) of 10 CFR Part 11.
Provide drawings or sketches that show the location ar.d construction of these devices and the overall tiedown system. Determine the ef f ect of the imposed forces on vital package compenents, including the interfaces between the tiedown devices and other package surfaces. Documented values of the yield stresses of the materials should be used as the criteria to demonstrate compliance with 9 71.31(d).
- 2. 5 Standards for Type B and large Quantity Packaging I
1y,[p./l l.
This section should state that the "tandards for type B and large quanti
- ackaging, specified in s 71.32, are complied with, as demonstrated in the following paragraphs.
2-2
- 2. 5. I toad Resist-ince Sho.< by an3 lysis or test thit the package, if regarded as a simple tseam supported at its end, along any major axis, can support a uniformly distributed load equal to five tirres its f ully loaded weight.
De ment values of the yield stresses of the materials should t;e used as the criteria to demonstrate complidnce.
2.5 2 External Pressure Sho. by test or analysis th.it the containmont vessel would suffer no loss of contents if the package were subjected to an enternal pressure of 25 psig.
- 2. 6 Normal Conditions of Transpcrt in this section, s t 3 t e th 3t the p ic.kage, when s uDj ec t ed to t he no rma l cond i t ions o f transport specified in Appendia A to 10 CFR Part ll, meets the stanJards specified in n 71.35 of 10 CFR Part 71, as demonstrated in the following paragraphs Tha package shauld te assessed aqtinst e ic h condition separately and a determination maJe that the applicable performarce re q u i r e rre n t s speci f ied in the regulations have t een sati s fied.
2.6.1 Meit The tr ermil evaluation f or the beat test should be r eported in Sec tion 3. 4.
l.1 Summary of Pressures and T empe r a t u r e s Summarize all pressures and temperatures, determined in t.h e therm 31 evaluation (Chapter 3), that will t,e used t o perf or m the calculations requi red f or paragraphs 2. 0.1. 2, 2. 6.1 3 a nd 2. 6.1. 2
?. 6.1. ' Differential Thermal [ 9 1nsion.
Calculate the circumferential.ind axial deforma-tions and stresses (if any) tnat result fren differenti3l thermal expansion.
Consider steady-state and trinsient conditions. These calculat ions must be suf f ic ient ly c wprehensive to demon-st r.ite pac k age integrity under norn il transport conditions.
_2. h. 1 3 Stress Calculitions. Calculate the stresses d;e to the com ined ef f ects of ther m l gradients pressure, and mechanical l o <id s. Provide sketches t h -i t sh9w the Configuration and dimensions of the memters or systems being an31yzed. and locate the points at which the st resses a re tie i ng ca lc u l a ted.
The antl;. sis s.
ald consider hether repeated cyc les of thermjl lojdings a
together with other loadings, will C 3us > ta* 1gue f ailar e or ex tensive accumul itim s of deformiticn.
- 1. 6.1. 4 Compariscn with Allowable Stre ses.
Pike the o pp r c p r i,i t e stress combinations and compire t he resul t i eg stre',es wi th the design criteria in paragrnh 2.1.2 of the application.
Show th.1t a l l the pe r f o rm.ince requ i rem.ents spec i f ied i n t f.e regul a t i ons h.iw e been sat i s f ied.
2.6.2 Cold Assess the package for the effects of a steady state ambient temperature of -40 F (-40 C).
Con 3ider t:oth m3terial properties and possit;la freezing of liquids under this condi t ion
- Identify, 2-3
for vital components of the package, the resultine mperatures and their effect on operation of the package. Brittle f racture should be considered.
2.6 3 Pressure Assess the package for the effects of external pressure equal to 0.5 standard atmospheric pressure.
2.6.4 Vibration Assess the package for the ef fect of vibrations normally incident to transport.
2.6.5 water Spray Assess the package for the ef f ects of the water spray test.
2.6.6 F ree Drop Assess the package for the effects of the free diop test.
The genPral comments in para-graph 2.7.1 also apply to this condition. (Note that the f ree drop test follows the water spray test.)
2.6.7 Corner Drep If applicable, assess the package for the ef fects of corner drops.
2.6.8 Penetration Assess the package for the effects of penetration. Note that the point of impact could be at any location on the exterior surf ace of the package.
2.6.9 Compression As applicable, assess the package for the ef fects of compression.
- 2. 7 Hypothetical Accident Conditions in this section, state that the package, when subjected to the hypothetical accident condi-tions as specified in Appendix B to 10 CFR Part 71, meets the standards specified in s 71.36 of 10 CFR Part 71, as demonstrated in the following paragraphs.
The hypothetical accident conditions are to be considered in the sequence specified by the regulations. Damage caused by each test is cumulative, and the evaluation of the ability of a package to withstand any one test must consider the damage that resulted f rom the previous tests.
It should be noted that a determination must have been made ia Section 2.6 that the ef fectiveness e
2-4
of the package has not been reduced as a result of the normal conditions of transport. Brittle f racture should be considered.
9
?.7 1 Free Drop The performance and structural integrity of a package must be evaluated for the drop orienta-tion that causes the most sesere damage. An orientation that results in the most damage to one system or component may not be the most damaging for other systems and components. For this reason, it is usea'l) necessary to consider several drop orientations. The minimum requirement ir that ocientations fcr v.hich the center of gravity is directly over the point of impact must be cor.sidered.
The assessment of the package may be l.,y anilysis, prntotype testing, model testing, or com-parison to a sir. ilar package.
a.
Analysis Calculations should be presented in sufficient d>'. ail to allow the results to be veri-fied.
Adequate narration and use of sketches and free body force diagrams should be included.
For equations used in the analysis, either the source should be referenced or the derivation should be inc iuded.
The analysis should show how all the kinet ic energy will be dissipated and which local deformation and dynamic forces occur during impact The response of the package in terms of 9
stress and strain to components and structural members should be shown.
The structural stability of individual members as applicable should be investigated as well as stress due to impact combined with those stresses caused by terrperature gradients, dif ferential thermal expansions, pressure, and other loads. Show that the perf ormance requirements of 10 CFR Part 71 are met.
b.
Prototype Testing Describe the test method, procedures, and target t h a t.e re used.
Indicate the p3ckage orientatico at time of impact.
If the parkage tested is not identical in all respects to the package described in the application, explain the differences and show that these differences would not af f ect the test re s> il t s.
fle s c r i t:e the m3terials used as substitutes for the radioactive contents during the tests.
Show that this substitution would not affect the test results. Consider the effects of internal decay heat and pressure buildup if these effects would have arisen witf the actual loading.
Indicate in a quantitative manner the daw ge caused by the impact and the results of any measurements that were made.
Include both interior and exterior d. mage.
Prov ide photographs of the damaged packaging.
Snow that the performance requirements of 10 CFR Part 71 hav,e been
+ f or the damaged package h
4 >
?-5
t.
Model Testing Describe the model ct rp letely and pro. ide detailed drawings that < hew its dimension <
and m it e r i.il s of constr uc t icn.
Specify the di~ensionil toler inces to which th.
ra e l ai, f at>r i c a t ed, and t errp ire these to the tolerances tt. it w i l l be thed f or t he protots po State ite scale factor thit w.is use 1 for tr e model.
Describ in dettil t h.
l iws of similitude thc ' were used for testing, considering time s(.il e meterial density, selocity at impact, and kivetic energy.
Justify thit the mo !e l test will gi ve (orm rv it ise results for peak q-force, n im imum de f or mat ion, and d i ss ip ited energy.
f or t he at tu tl model tests, pro s ide al l the informilion requirej for i ten b ab ve.
Cor r e late the dimige N ne 'o the model with dimage to 1 prototype, and show that the prototype would he efequ ite t o meet all the per f ormance requirements of 10 CF R Pa r t /1.
d.
Ceapirison to similar Osk if s Ine compirison most defro ns t ra t e tha' tt preposed pickage it, in.ill ret,wcts, tetter
' h in cr e qi,.i l to t t.e p ic k. ige pie on.ly approsed and that t he prepased p u h. ice r in m*et all the regulatory performince requir aents The c c mpar isca ct the too p Kkages should provide t le f o l l ew i ng !e t.111 s (1) The dimens ions meterials and con f it arat ion-et both packages.
(?) T he overa l l we ight n f bo t h p ic k ige
( !) I h, we ight arul f orm o f the contents of hot h pac k yes,
(1) Ih it the packag s will has, a simil.ir response to the
- >et i f i ed t es t s,
(5) Thit the forces actirq on ill vitil s.i f e ' ) system, and components of t he pri' posed packay ar e less than the tested package or that all w i t.il u f et y systems and components of the propos ed p ic uqe h.is e s a t f ic ient s t ruct ura l integr i ty, and (6) Ih tt the pr opo >ed p.t h age will meet a ll the r egulatory I erf or mance r equire"ents
- 2. / 1.1 fod Drop.
Assess the P R k. ige f or the ef f ects of the end drop test.
'. /. _1_. ? Side Drup. Assess the p akage for the ef f ects of the side drop t( s t.
- l. 7.1.1 Corner Orcp. Assess the p ic kage f or the ef f ects of the corner drop tt
/. /.1. 4 Chlique Drog Assess the effects of oblique drtps, or provide information th it shows that the end, side, jnd corner drops are more dam iging to all sy stems and cottponents vi tal to safety.
- 2. /. i. 5 Suv irr of Results.
Discuss the condition of the package after each drop test.
SLmmarize the extent to which the packaging would be dim tged in each orientation.
O
~
2.72 Puneture Assess the et f ects of the puncture test. Consider hcth local damige near the point of impact and the overall ef f ec t on tt:e pac k age.
Note th.it t'e paint of impact could be at any location on the ex terior sur t i f o f t r e p ic k 1ge.
It is part it ularlj i t'.p o r t a n t that a l l v al ve s and t i t t ir.gs necesury for cont a ir. ment t e considerel M s'. of t!e general c oaime n t s i n pa ragra;,h 2.l.1 also apply to this test condition.
- 2. l. 3 Therm 11 Inc t %rm i: test should follow t'e tree drop out punct ure tests and should be reported in ec t i.>n 3.$.
A 7. 3.1 son y of Pressures an:t Temper.itures sumarize 411 of the temperatures a mi pre <sures, as determined in the therill e s '.l u it ion (Ch 1pter 3) of the,ipplication, th1t 1re used i n p ir.u;r aph. ?. /. 3. J, 2. l. 3. ; and 2. /. 3. 4.
. /. 1. ' Diff.r+ntiil l he ra a l E pinsiun.
Calculite the circumferentiai and axial defor m t i o n '., ind stresses (if any) that result trum differential t herrail e = p ins icn. Cons ider peak con-ditions po s t i i re s t eady s t.1t e con f i t i on > an i all transient con fit ion' 2 /. 3 3 Stres, Calc ul 1t ions. C.ilc u l it e t he s t r e'se s d..e to tr erma l gr 1Ji ent s, di f f erent i al e pin, ion, pr
,sure, and other En h m i c a l load;
- 'ru v i de sketchet shuainq cuntiguration.in !
dim-nsinns of tre men t;e r s et s, sten der in.est ig it ion, a:n1 locate the p: int, at whic h the O
stresses ar e t.e i ng calcul ated.
../.l..
Coroarison with Alleaible Str esses.
M ike the a; p cpriate stress ccmbination>
U.1 c m a r e t he result ing strersec.i t h the de -ign riterii i n p iragraph 2.1. 2 of t he apDlic1 tion.
W. that ill th pe r f o rm.inte reqai r evn t s spec i f ied in t h+
regulat ions h i.e been sat ist ied.
- 2. l. 4 hiter 1rnersion Assess t *' e ettects and comey.ences of the oiter irmer3+
test ( cn.fi t ion for fissile
. Kkige,
?. l. 5 kmr'iry of D im ige Discu; the i.i f e t y of the package attei th.ic c i de n t test equtoces S umm.i r i z e the entent t o 4 hic h v i t a l s if e t y sy s tems a"d component s h ie been d im ed
- 2. R.
5: ecial fmm As apolicable, in this section **.en special tom is claimed, state that the material meets special f orm requirements given in paragr1ph /1. 4(o) wnen subjected to the applicable test condi-t icas of Appendi = 0 to 10 CF R P.irt /1, a s downs t rated in the f o l i m i ng pa r.1 graph s A a
- r 1 Ib It sau 2-/
2.8 1 Description Describe the chemicol and physical form.
frovide cetailed drawings of the encapsulation showing the dimensions, materials, and manner of ccnstruction.
2.8.2 Free Drnp Assess the package f or the et fects of the f ree drop test.
2.8.3 Percussion Assess the package f or the ef f ects of percussion.
2.8.4 Heating Assess the package for the ef fects of heating.
2.8.5 Imrre rs i on Assess the package f or the ef fects of immersion.
2.8.6 S umma ry Provide results of above analyses, and show that requirements of paragraph 71.4(o) of 10 CFR
,i Part 71 are met.
2.9 fuel Rods When required, fuel rod analyses or simulated tests should show tha* the mechanical integrity of the cladding is adequate to provide containment of the pellets and gases for both normal and hypothetical accident conditions of transportation. End-of-life fu rod measures and maximum volumes should be clearly stated and considered in the analysis. Fo mal condi-tions of transport. the cladding shuld he capable of withstanding the resulting ! cads without yielding. For the accident damage "Osts, the cladding integrity may be demonstrated by using either plastic or elastic analyses.
Possible creep rupture and fatigue failure should be considered.
2.10 Appendix This appendix should include information such as justification of assumpti^ns or analytical procedures, test results, photographs, computer program descriptions and input / output, reference lists, and applicable pages f rom referenced documer ts.
c
(
s, c 2-8
3.
THERMAL LVALUATION This chapter of the application should identify, describe, discuss, and analyze the principal thermal engineering design of the packaging, components, and systems important to safety and to compliance with the perf orman'e requirements at 10 C F R Pa r t 71.
3.1 Discussion Describe the significant thermal design features and operating characteristics of the package.
The operation of all subsystems (e.g.,
auxiliary cooling systems, expansion tanks) should be discussed. Summarize the significant results of the thermal analysis or tests and the implication of these results on the overall package. State the minimum and maximum decay heat loads assumed in the thermal evaluation.
- 3. 2 Summary of Thermal Properties of Materials List the thermal properties of all materials used in the thermal evaluation. References f or the data cited should be provided.
- 3. 3 Torhnical Spn it" cations of Components include the technical specifications of package components. For example, in the case of valves or relief valves, the operating pressure range and temperature limits should be includel The properties of fabricated insulation and coatings should be tabulated. Test data should be supplied in support of performance specifications and should be presented in detail in Section 3.6.
3.4 Thermal Evaluation for Normal Conditions of Transport Appendix A to 10 CFR Part 71 defines the norma! conditions of transport. These conditions are to be applied to the test item or analytical model.
The test item or analytical model should be described. Particular attention should be given to justifying the use of simplifying or scal.nq assumptions. When the package design involves various operating modes or configura-tions such as different fuel loadings and dif ferrat coolants, each mnde must be evaluated within its operating range to determine the adequacy cf the design.
3.4.1 Thermal Model 3.4.1.1 Analytical Madel. Describe the analytical thermal model in detail. The model should include gaskets, valves, fuel assemblie,, and the overall package. Modeling assu ;,t ions should be f ully justified.
- 3. 4.1. 2 Test Model.
Describe the test item and procedures used.
Provide the details of 8
the procedures used to correlate the test data to the thermal environment for normal conditions 3-1
of t r inspor t, as def ined in Apperalix A to 10 CFR Part /1.
Temperature data should be tak en f ror gaskets, valves, and other containnent bound 1 ries as well as f rom the o,erall pickage.
3.4.2 Maximum Temperitures i
list the maximum temperatur e dis trit;ution f or the package f or nor mil condit ions of tr $nsport,
including the contents, contairment vessel, shiolding material, gaskets, valves, etc.
3.4.3 Minimum Temperatures L ist the minimum temperature distribution for the pack jge f cr normal conditions ut transport.
This evaluation should include the minimum deca / heat load that will tie transported. When a de ly be lt load greater than zero is required for safe operation, assurance of that hett load must be provided.
The temperatures of signi ficant c omponents such as q1skets and valt as should be reported.
3.4.4 Maximum Internal Pressures lhe conditions within the range of normal conditions of transport that result in the worst internal pressures or the worst combination of therm 11 l o,1d i ng s should be identified. The internal pressures for these conditions should be determined. The evaluation should consider the effects of phase change, gas gener1 tion, chemical decomposition, etc., as well as fiuid e=pansions and compre;sions.
The additional pressure buildup that would result from fuei rod failure while in transport shaula also be considered it the ability of the rods to provide con-ta inment under all c ircumstances tannot t;e demonst rated.
3.4.5 Ma<imum Thermal Stresses Determine the conditions within the range or normal conditions of tr1nsport that result in the worst combination of thermal gradient and isothermal stresses. L ist t he resul ting temperature distribution.
3.4.6 [v a lu ition of Pac,
,e Performance for Normal Conditions of ! ra g spo r t Evaluate the package performance, including system and subsystem operation, f or normal con-ditions of transport with respect to the results of the thermal analysis or tests performed.
Take into account significant conditions to be found in the ranges bounded by the minimum and maximum ambient te'rperatures and minimum and maximum decay heat loads. Compare the results with allowable limits of temperature, pressure, etc.
for the package components.
['e s i gna t e the information that is to be used in other chapters of the review.
Present the informatioa in summary tables along with statements anJ appropriate comments.
3.5 Hypothetical Accident Thermal Evaluation In this section, the effects G' the hypothetical accide-t thermal condit;on cn the package should be evaluated. Appendix B to 10 CF R Part 71 defines the hypot e ic 1 a c rf( t conditions, 3-2
which are to be applied sequentially. The thermal test f ollows the f ree drop and puncture tests.
Discuss the tests or analytical procedures used to evaluate the package performance for the hypothetital thermal accident condition. When the package design insolves various operating modes or conf igurativos such as dif f erent f uel loadings and dif ferent coolants, e3th mode must be evaluated within its operating ranges to determine the adequacy of the design.
3.5.1 Thermal Model
- 3. 5.1.1 Analytical Model. Describe the analytical thermal ~< del in detail. The model should include g3skets, valves, ruel assenblies, and the owerall pack 3ge.
Modelinc; assumptions should be f ully justified.
3.5.1.2 Test Modol.
Describe the test item and procedures used.
Provide the details of the procedures used to correlate the test data to the thermal envir onment for the hypothetical accident conditions, as defined in Appendix B to 10 CFR Part 71.
Temperature data should be taken f rom gaskets, valves, and other containment boundaries, as well as f rom the overall package.
3.5.2 Packago Conditions and Environment Describe a,d discuss any damage to the package resulting from the free droo ur puncture tests The effect of any such damage on the package thermal performance is to t;e evaluated.
The worst possible package conditio.i from a thermal standpoint will be cnosen from the range of damap ccnditions following the free drep and puncture. This worst case i: to be used in the 9
thermal analjsis.
3.5.3 Pack 3ge Temperatures lhe tr3nsient results of the f.hormal analysis or test should be presented. The temperatures reported should incluje those temperatures at lccations in the package that are significant to the safety analysis and review.
The temperatures for such items as contents, gaskets, valves, and lead shielding are especially important and should be reported. The cniculations of transient temperatures should trace the temperature time-history up to and somewhat past the time at which temperature maximums are achieved.
It may be assumed that visible f lames f rom packaging material are extinquished in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 3.5.4 Mnimum Internal Pressures Determine the maximum internal pressures that tesult during the fire test and cooldoon (include the added pressure caused by fuel rod failure during transport). The pressures that result in the most severe loading in combination with any other leads developed should be deter-mined. Provide details of the pressure calculations. !hese details should include temperatures and quantities of fluids as well as the associated fluid volumes. Where chemical reactions or phase changes occur, the fellowing should be discussed: (a) the reaction or phase change mechanism, (b) the reactants and products involved, (c) estimates of the extent ar.d the rate of reaction or phase change, and (d) the consequences of the reaction cr ph3se change. IN addi-tional pressure buildup due to f uel rod f ailure during the fire should also be considered.
144 156 3-3
If the a skage is tested, the pressure determinition can be neglected in s o.. a C.ises Ihr internal pressure rieed not t;e determined if actual test conditions prcp rly.imulate the condi-tions thit m;uld cause the severe pressure t;u i l dup in cavities.
This approach is acceptable
. hen similarity i s demons t rat ed tmt ween the test item and casks f or stKh things as cavity f luid, components, ind internil geumetries 3. 5. ')
Maximum T he r m.il Stresses Determine the most severe thermal stre<< conditions that result during the fire test and
>ubsequent cuoldown.
Report the tenerature< corresponding to t he ml4 imum thermal stresses.
If the ptchage is te sted in such a way that similarity i s demonstrated tietween the test item ind the cask concerning inter n il pr essure, the max imum thermil stresses need not t>e calculated.
3.S.6 ivaluttion of Pac k age Performance for tfe Hg othetical Accident ] ermal Conditions Evaluite the packaq" performance, includirq system and subsystem operation, for the hypothetical accident thermal conditions with respect to the results of the thermal analysis or tests performed. Compare 'he results with allowable limits of temperature, pressure, etc., for the package components.
Estimate the dam. ige to the package either from interpretation of the analysis or from test observation. This assessment should incluJe structural dimage, t're.ich o f containment, and loss of shielding.
Designate the inform 1tico to be used in other chapters of the review.
This inf orm.ition should t,e presented in s t.mma ry tables and statement s with appropriate comments.
The comments are to include destinatiun and use inf orm.ition and the specific conditions that the data simulate.
3.6 Apper fi x y
This appendin should include inf ormation such as justif icat ion of assumptions or anitytical procedures, test results, photogra;;hs, computer program descriptions and input / output, and appli-cable pages f rom ref erenced documents.
S 3-4
B 4.
CONTAINMENT This chapter of che appi cation identifies and discusses the package containment for the normal conditions of transport and the hypothetical accident conditions.
4.1 Containmer.t Boundaiy identif y the containment boundary claimed f or the package.
4.1.1 Containment Vessel A summary of design specifications f or the containtneat vessel should be provided.
4.1. 2 Containment Penetrations Identif y all penetrations into the primary containment. Provide a summary of the perf ormance specif ications f or all components that penetrate the cor.tainment boundary.
4.1.3 Seals and Welds 9
Identify all seals and welds that affect the package containment. A summary of the design specifications for these seals and aelds should be provided.
4.1.4 Closure Identify the closure devices used for the containment vessel.
Specify the initial bolt toraue that will be required to maintain a positive seal during normal and accident conditions of transport.
4.?
Requirements for Normal Conditions of Transport Summarize and use the pertinent results of the analysis or test perf ormed in Chapters 1 and 2 to demonstrate the package containment under normal conditions of transport as defined in Appen-d i x A to 10 Cf R Pa r t 71.
4.2.1 Release of Radioactive Material Show that there will be no direct release of radioactive material f rom the containment vessel.
4.2.2 Pressurization of Containment Vessel 144 158 Any mixture at vapors or gases that could form in the containment vessel should be identified.
Show that any increase in pressure or explosion within the containment vessel, due to these vapors or gises, could not signi f icant ly reduce the pac kage ef f ect iveness.
4-1
1./.3 (orilint Cont imi n.it s on
[stimite the rafioittise c i nt imirat ion of the p r i m.i ry ( co l in t. Y,o w thtt t h+
. >n t i n i e s t ino doe s no t e s t eed t he m i r in,um le,els specified ' n p ir aq' iph 11. ;M.i)(1) of 10 TI R Part
'l
- 1. '. 4 C oo I.j_rg i e-show that ther' will te no le >,of c oo lant tueter the norm;l. o.,d ; t i o m, of t r.in ' ; u no that there will he n<>
, c o t 109 o f the (en'.ainment v. s s
- l d i rec t !,
t o t.te.i' chere.
i 4.1 Cont.
..nt Regairements for t h.
6!,po t he t i r_ i l Ac t i rb r.t lordition S umm.i r i le.i r al u..
the pertinent results :i t th+
anilysis or t e <. t pe r t o r n,ed in t h ipt er s /
iruj 1 to demonst r a te the p.ith. ige t o n t t i rm. cot under the h y p't het i c.i l a1 cident ( o r d i t i or, defired in Appendt. H to 10 U R D.ir t /1.
4.1 1 fis', ion Cis Products istabli-h t he m.i imom qu in t i t y of fissio;1 o i, pi odoc t, t h.i t could h, i, ii 1 ;b le for re le i.e t o t he t ont a inment we
,e l under t' e hyp it ta t i c s l 1: cident < rd i t ii o >
4. 1. / ke l e.i', e s of Content <-
Show that ther e c an be no r e l e.ise of r id i o.ir. t i v e ma t e r i a l s e'tept for g i >e 3.ind c ont n in it ed t oo l. int, ex t eedi ng t he m ix imum qu int i t ies de f i ned i n p ir igr.tph /1. N(.i)( / ) o f 10 CI R Pa r t
'l.
4.4 Ag endix Ihis ij yle'lif i.* '. ht)J I(l i flE ! LJif e Supp(]TI l f Hj 511 t ('I 'r' i l l i,rl.i f li j anil y i i 's i
) A l,i i s 4-2
B 5.
5HIELDIN3 EVAtUAllCN This chapter of the application should identify, describe, discuss, and analyze the principal shielding design of the packaging, componelts, and systems irrportant to saf ety and necessary to comply with the perf ormance requirements of 10 CF R Part 11.
5.1 Discussion and Results Discuss the significant shielding design features of the package and the adequacy of the shielding evaluation.
Table 5.1 should be completed. For packaging desigard far spent fuel transport, assumed f uel burnup, power density, and cooling times should be statec.
5.2 Source Stecification in this section, st3te the contents and the gamma and neutron source ter ms used in tre shielding analysis.
- 5. 2.1 Gav.i Source B
decay State the quantity of radioactive m :terial included as contents, and tabulate the gammi source strength (MeV/sec anJ photons /sec) as a function of photon energy. Describe in det ail the method used to determine the gamma source strength and distribution.
5.2.2 Neutron Source State the ou3ntity of radioactive oiterial included as contents, and tabulate the neutron source strength (neutrons /sec) as a function of energy. Describe in detail the method used to determine the neutron source strength and distribution.
- 5. 3 Model Spec:fication In this section, describe the model that was used in the shielding evaluation.
5.3.1 Description of the Radial and Axial Shielding Configuration loclude sketches, to scale, and dimensions of the radial and v ial shielding materials.
Dose point locations for the various calculations exterior to tne package should be shown relative to the source regions in the sketches supplied. Voids or irregularities not taken into account in the model should be discussed in detail showing that tle resultant dose r,ites are conservative. Di f f erences bet.een the codels for the norm a l conditions and the accident conditions of transport should be clearly identi f ied.
5-1
TABLE 5.1 1
SUMMARY
OF MAXIMUM DCSE RATES
(
(mR/hr) 3 Feet from Package Surface Surface of Package Side Top Bottom Side Top Bottom Normal Conditions Gamma Neutron Total Hypothetical Accident Conditions Gamma Neutron Total 10 CFR Part 71 Limit ----
1000 1000 1000 5.3.2 Shield Regional Densities l
The material densitit, (g/cm ) and the atomic number densities (atoms / barn cm) for consti-tuent nuclides of all mateai als used in the calculational models for the normal and accident analyses are to be given in this paragraph. The source of the data f or uncommon materials should be referenced.
5.4 Shielding Evaluation Provide a general description of the basic method used to determine the gamma and neutron dose rates at the selected points outside the package for both the normal and accident conditions of transport. This should include a description of the spatial source distribution and any com-puter program used, with its referenced documentation. The basic input parameters should be discussed in detail. The basis for selecting the program, attenuation and removal cross sections, and buildup f actors should be pr ovided. Flux-truose rate conversion factors as a f unction of energy should be tabulated. Data are to be supported by appropriate references.
5.5 Appendiu This appendix should inclu,1e information such as justification of assumptions or analytical procedures, test results, photo,raphs, computer program descriptions and input / output, and appli-cable pages f rom referenced documents.
5-2
D 6.
CRITICALITY f'!ALUATION This chapter of the application should identif y, describe, discuss, and analyze the principal criticality engineering physics design of the packiging, components, and systems importai L to saf ety and necessary to comply with the perf ormance requirm ents of 10 CFR Part 71.
These require-ments are summarized in Table 6.1.
6.1 Discussion and Results Discuss the significant criticality design features of the package and the adequacy of the criticality evaluation. Table 6.2, summarizing the criticality evaluation, should be included in this section.
6.2 Package fuel loading Provide a summary table stating the maximum f uel loading and f uel parameters for the package f or normal and accident conditions of transport.
- 6. 3 Model Snecification This section descrit4 > the model used in tho evaluition.
6.3.1 Description of Calculational Madel Dimensioned sketches, to scale, or the geometric model used in the calculation are to be given. The sketch should identify the miterials used in all regions of the model. Differences between the actual package configuration and the model shauld be identified, and the model should be shown to be conservative. Dif f er ences between the models f or the normal conditions of transport and the accident conditions of transport should be clearly identified.
6.3.2 Package Regional Densities The material densities (g/cm ) and the atomic number densities (atoms / barn-cm) for con-stituent nuclides of all materials used in the calculational models for the normal and accident analyses are to be given in this paragraph. Fissionable isotopes are to t;e considered at their most reactive credible concentration.
Masser, for all regions are to be given consistent with atomic number densities and volumes occupied.
6.4 Criticality Calculation this section should describe the calculational or experimental method used to determine the nuclear reactivity for the maximum fuel loading or other maximum contents loadings intended to be transported in the package.
6-1
8 FABLE 6.1 REQUIRED NUMBER Of PACKAGES TO BE DEMONSTRATED AS SUPCRITICAL UNDER SPECIF IC MODERATION AND REFtECTION CONDITIONS AS PER SECTIONS 71.38, 7I.39, AND 71.40 OF 10 CfR PART 71 CONDITIONS OF SHIIME NT FISSILE CLASS NORMAL CONDITIONS ACCIDE NT CONDITICNS (No more than 5% reduction in the (All packages damaged as per hypo-total effective volume of the thetical accident (HA) specifica-pickaging on which nuclear safety tions) is assessed.)
I g imited number of packages are U
250 packages are to remain subcri-to remain subcritical with opti-tical in any arrangement under HA mum interspersed hydrogenous conditions with optimum inter-moderation. No water reflection speised hydrogenous moderation and necessary.
clnse reflection by water on all sides of array.
II Five times the number of packages Two times the number of packages to to be shipped,re to remain sub-be shipped are to remain subcritical critical in any arrangement when in any arrangement under HA condi-this array is closely reflected tions with optiraum interspersed by water.
hydrogenous moderation and close reflection by water on all sides of array.
Since the maximum value of the Transport Index (TI) for an individual package of Fissile Class II is 10 and the TI equals 50 divided by the allowable number of packages, 5 is the smallest value for the maximum allowable number of packages in a shipment. Therefore, the minimum number of packages in the array that must be considered in the criticality analysis is:
5 r. 5 or 25 packages 2x 5 or 10 packages for normal transport for accident conditions III One shipment of packages is to One shipment of packages is to remain subtritical when it is in remain subcritical under HA condi-contact with an identical ship-tions with optimum hydrogenous ment and the two shipment array moderation and close reflection is reflected on all sides by by water.
water.
144 163 6-2
TABLE 6.2 SUMMARf 0F CRITICALITY LVALUATION Fissile Class (I, !!, 311)
Fissile Class NORMAL CONDITIONS I
11 Ill Number of undamaged packages calculated to be subcritical (F issile Class I must be infinite; Fissile Class 11 must be at least 25; and Fissile Class 111 must be at lent identical shipment.)
Optimum interspersed hydrogenous moderation (required for Fissile Class 1)
Closely reflected by water (required for Fissile Class 11 and 111) 3 Package size, cm ACCIDENT CONDITIONS Numoer of damaged packages calculated to be sub ritical (F issile Class I must be at least 250; fissile Class 11 must be at least 9
10; and Fissile Class 111 must be at least 1.)
Op t i mt.m interspersed hydrogenous mnderation, full water reflection Package size, cm Other Transport Index (must not excetd 10 for Fissile Class 11)
\\he \\6h 6-3
6.4.1 Ciltulatienil or F qerimental Pettnut A
i s for se let t iny t he pro:p am,in 1 t r o,s set t ions shouldta discussed. I f in e sper imenta l method -is u - ed to.etermine th con plianc e of t he p it k.sye w i t h t r i t it a l i t y t equ i rerrent s, inc lu fe i complete descr iption of tre e periment and a disc uss ion deme s t r.it i ng t h t t it conservatively t.ther int o ac c ount t he norm il and,ict ident condi t ions of t ransport f or t he p ic k. ige.
- 6. 4. ' fuel l o.idi ng or Ot her Cont ent s l o id i ngp t im i z at ion (Jemonstrite that t he cor r ect fuel loading or ot her conterts lead ing f or t t+ ma x imum r e.u t i v i t y has iten evalu ited f or ooth the, i ng l e p ic h aq..ind a rt ry s o f p ic k.igo s f o r no r m.il tnd.ic c i den t c omf i-t ions of trinsport. Approximation. boun fary condit ians c a lcul a t iona l conv ergenc e c r i te r i.i, md c ross sec t inn aitjustmont s are to L ' i t emiled and di sc ussed.
The requirements of a /1.33, /1. 3 4, 11. B, and 11. N o f 10 Cl R part /1 should te,atisfied tur a single p at h sqe. The requirements of n 11. 3 / in i /1. E, /1.34, or /1. 40, as approp r ia t e. ,hou ld be uit is t ied f or a n a r r.t v. h.4.3 Cri t ic ali t y Pesult s Results of the reac t i v i ty calc ul<it ions es tabli sh ing the mos t re.ic t i ve c onf iguret ions f or t he s ingle p ic k ige and irrays of pack iges f or t:oth norma ! and.itc ident c ondi tions of transport should t,e d i s p l.t yed in t it+ular and grwhic f orm. Just i f ic it ion should be provided f or any interpo lat icos and extrapolations A discussion of the validity and tnoservatism of the analysis shool<! be included. The tias est.iblished with the benchmark c.11 c u l i t i o n s in %c t ion 6. 5 should tw taken into ac count. f, 5 Critical Brnchmara f gerirrent s This sec t ion provides justi f icat ion f or the s alidity of the calculation il method and neutre.n cross section values used in the analysis Ly presenting the results of calculations f or selected critical t enchmark experiments. 6.5.1 Henchmirk E=periments and Applicarfility Provide a general description of selected critical benchme-k exper imrots that are to be analyzed using the method and cross sections given in p.irap aph 6.4.1. The applicability of the benchmarks in relation to t he package and its contents should be shown. All similarities and di f f erences should be noted and resolved respectively. References giving full documenta-tion on these experiments should be provided. h 6-4 6.5.2 Cetails of tho Benchmark Calculations Actual nuclear and geometric input parameters used for the benchmirk calculations should t>e providod. 6.5.3 Results of the Henchmark Calculations Provide the results of the benchmark calc u l it ions. E stablish and proside a discussion of any calculation bias. 6.6 Append i x this appendix should include inf orm.ition >udi as justif ication of assumptions or analy tical p r ocedure s, t es t resu l t s, phot ograph<., compute r pr ogram desc r ipt ions.ind i nput/out put, and a;;p l i-cable pages f rom ref er enced docunnts. 9 144 166 9 6-6 7. OPE RAT ING PROCE DURE S This chapter of the application should desciibe the operating procedures to be used in the preparation f or and perf ormance of the processes of loading and unloading the package. The discus-sion of these procedures should be presented sequentially in the actual order of performance. At a "tinimum, this chapter should demonstrate the ability to comply with the operating procedure requirements speci f ied in Subpart D to 10 CF R Part 71. 7.1 Procedures for Lo3 ding the Packige The discussion should include inspections, tests, and special preparations of the package for loading. If applicable, a detailed description should be presented of the procedures used to ensure that liquids such as shield water and primary coolants are filled into their respective cavities, in compliance with the design specificatio75. Cetails should also be provided of the procedures used to remove residual moisture from cavities designed to be dry. The effect;veness of the procedures should be evaluated.
- 7. 2 Procedures for Joloading the Package This section should include-ir ~ olons, tests, and special preparations of the package 9
contaminated coolant, and solid contaminants should be discussed. for unloading. As applicable, the procedures used to ensure safe removal of fission gases, Also as applicable, describe any required cooldown procedure, and show that it does not affect the continued use of the package.
- 7. 3 Preparation of an Empty Package for Transport This section should discuss the inspections, tests, and special preparations of the packaging necessary to ensure that the packaging is properly closed, decontaminated to prevent the inadvertent spread of contamination, and delivered to a carrier in such a condition that subsequent transport will not reduce the effectiveness of the packaging (e.g., damage to sealing surfaces caused by the f reezing of muisture not properly removed).
7.4 Appendix This appendix sh:uld include supporting documentation, detailed discussions and analysis of procedures, and graphical presentations. 7-1 D 8. ACCEPTANCE TESTS AND MAINTENANCE PR9 GRAM This chapter of the application should discuss the acceptance test and maintenance program to be usea on the packaging, in compliance with Subpart D cf 10 CF R Part 71. 8.1 Acceptance Tests Discuss the tests to be perf ormed prior to the first use o. the package. d.1.1 Visual Inspection The visual ilspections to tw perf ormed and the intended purpose behind each inspection should t>e discussed. State the criteria for acceptance for each of these inspections as well as the action to be taken if noncompliance is encountered.
- d. l. 2 Structural and Pressure Tests Descritie the tests tn be perf ormed. Present tr e acceptance criteria. Describe the action takan when the prescriF d criteria are not met.
An estimate of the sensitivity of the tests should be prov ided. 8.1.1 teak Tests Describe a leak tests 'a be performed. Leak tests should be perf ormed on the containment as auxil:ary eqc pment such as shield tanks. Descrite the criteria f or acceptance vessel as well i ind the acti.e to be taken #f thr e-iteria are net met. Estimate the sensitivity of these tests, and give the ba: is f or the r,t imate 9.14 Compnnent Tr its Discuss the tests for those components to be tested. Provide acceptance criteria c,d discuss the action to be taken if the criteria 3re not met. 8.7.4.1 Valves, Rupture Discs, and f luid Transpc rt Devices. These components should be tested under the most severe service conditions for which the package design assumes their acceptable performance. When the tests are presumed to adversely affect the continued perform-ance of a corponent, the results of tests on components of the same model and type may be substituted. 8.1. 4. ? Gaskets. Gaskets should be tested under conditions simulating the most severe service conditiors under which the giskets are assumed to perform. Since these acceptance tests 9 may degrade toe performance of either the gasket under test or the package into which it is assembled or both, the tests are ont necessarily performed cn g3skets or packages ;o be put into 8-1 service. The simulation system must ens Jre adequate representation of those conditions that .culd prevail if the actual system were used in the test. In accordance with paragraphs 4, 7, and 18 of Appendix E to ID CFR Part /1, the manufacturer of the gasket must maintain a quality issurance program adequate to ensure that acc ?ptance testing of a given gisketing desice is equivalent to acceptance testing of all gaskets supplied and identified by that manufacturer as that model g3sket. 8.1.4.3 Miscellaneous. Any ccmponent not listed in p 3ragraphs ff. l. 4.1 and 8.1. 4. 2 whose failure would impair the pack 3ge effectiveness should to tested under the most severe conditions f or which it was designed. 5ince these acceptance tests may degrade the performance of either the component under test or the system into which it is assembled or both, the tests are not necessarily perf ormed on components or systems to be put into service. The simulation system should ensure adequate representation of those conditicas that would prevail i f the actual system were used in the test. Furthermore, the manufacturer of the component should maintain a qu11ity assurance prugram adequate to ensure th1t acceptance testing of a given component device is equivalent to acceptance testing of all devices supplied and identified by that manufacturer as that model device. S. l. 5 Tests for Shielding Integrity D i scus s t'. ' ?sts t o be perf ormed to establish shielding f or both gamma and neutron sources. The acceptance cr,teria as well as the action to be taken if the criteria are not met shou d be 1 de s c r i tie d. 8.1. f> Thermal Acceptance fests Discuss the tests to verify thit each package performs, within some defined variance, in accordar,ce with the results of the tr.ermal analyses or tests f or normal conditions of transport. 8.1.6.1 Discussion of Test Setup. Describe the tests. The description should include heat source, i n s t r t.me n ta t i o n, md schematic showing thermocouple and hoat source locations as well as the placement of other test equipment. Estimate the test sensitivity based on instru-mentation, test item, and cnvironmental variations. 8.1. 6. 2 Test Procedure. Discuss the prcredJres used in te< ting and data recording. Report the frequency of data recording during the test. The criteria used to define the steady state (thermal equilibrium) conditiun of the test item should also be discussed. 8.1.6.3 Acceptance Criteria. Discuss the therm 31 acceptance criteria and the method emp'oyed tu compare the acceptance test results with predicted thermal performance. Discuss the action to be taken if the thermal acceptance criter4 rG 'ot met by a packaging unit. 8.2 Mainte This section should describe the mainto. o r u :, - ' e 2.o ansure continued performance of the packaging. The program should include per:Jic testing, insaector[g nd e .ement j 8-2 schattles as well as criteria for replacement and repair of components and subsystems on an is-needed basis. ' t_ri. '.u r a l and Pressure Tests 3.2.1 L ssribe the test; to be performed and the f requency of perf ormance. The instrumentation and test sensitivity should also be described.
- 3. 2. 2 Leak Tests Describe the tests to be per f ormed and the f requency of per f ormance. Estimate tha sensitiv-ity of these tests.
8.2.3 subsystems Maintenance Describe the test and replacement schedale to be used for packaging suDsystems (e.g., luxiliary cooling systems and neutron shield tanks) whose inadequate performance could impair the total package safety. Justify the schedules established, using verifiable test or manufac-turers' data. 3.2.4 Valves, Rupture Discs, and Gaskets on Containment Vessel Specify the test and replacement schedule to be used for these components. Justify the schedules established, using verif iable test or manuf acturers' data. 9 3.2.5 shieldig Describe the test and inspection schedales, as well as the corrective action to be used to ensure adequate shielding perf ormance. Both gamma and neutron sources should be considered. 3.2.6 Th -mal Describe the tests prcposed and the frequency of these tests that would be performed on the total system. Show that the proposed test f requency will detect thermal perf ormance degrada-tion of the packaging prior to compromise of the pickage safety. 3.2.7 Miscellaneous Describe any additional test not considere 1 previously that should be perf ormed periodically on comr onents and subsystems. ! } l 8-3 UNITE D ST ATE S NUCLEAR REGULATORY COVMISSION b W ASHING T ON. D. C. 20555 p OF F ICI AL D USI N E SS US NUC LE A R R E GUL A TOR Y PE N ALTY FOR PRIV ATE USE. $3M C O "" ' ' S ' 0 " U S WL L J O O l I a a