ML23058A281

Part 1-Response Acceptance Review, 2-23-23, Document No. No. 3-1 (Non-proprietary), Summary of Change of SAR for JRF-90Y-950K

ML23058A281
Person / Time
Site:	07103036
Issue date:	02/23/2023
From:	Boyle R, Neely R Edlow, US Dept of Transportation (DOT), Office of Hazardous Materials Safety
To:	Garcia-Santos N Storage and Transportation Licensing Branch
Shared Package
ML23058A255	List: ML23058A279 ML23058A281 ML23058A283 ML23058A284 ML23058A285 ML23058A286 ML23058A287 ML23059A252 ML23059A254 ML23061A185 ML23061A186
References
EPID L-2023-DOT-0000, CAC 001794
Download: ML23058A281 (3)

Text

Outline ofDesign Approval for Nuclear Fuel Transport Package using Type RF90Y 950K Transpoi Colltainer Outhne This transpon container has been used to transpoA new ttels for research reactors from France and other countries since 1991(the 01dest one was manuFactured in 1991),and tO transport iow ilradiated fuels to the .S,, vhile taking necessary hcensing procedures such as having periodica y renewed the approval period and having applied for approval amendment fbr addition of contents (Spent fue .

With domestic adoption of the 2018 edition of IAEA Regulations for the Safe Transpo of Radioactive Mtterial,"the rcgulations inctuding thosc known for O site Transport Regulations were revised on January l, 2021 to add considerations of aging during storagc 6f transpon containers and during use of nuctear fuel transpon package(statuS With contents ioaded in a transport container).In accordance with this revision,we have decided to add a description ofthe resuits ofconsiderations and evaluttions of aging in he attachment which explains safety(an item to be dcscribed in an attachment)and tO delete the registered contents which will not be transponed in future and apply for the registration.In addition,it was decided that this apphcation was to be submitted as a new applicttion(appliCation for design approval)in acCOrd mcc with the suidance from thc Nuclear Re8ulation Authorlty.

The deletion of registered contents and the aging cffccts do not need to be considercd in conflkliling comphance vith the technical criteria,and therefore the results ofthese safety analyses (StruCtural analyds,therrnal analyds,se h8 an ys ,shemhg analySis,and critic ity andys )

remaln unchanged.

1.Deletion ofregistered contents without a plan oftransportation in the future Curent Contents(16 types) Contents in Future(8 types) Largest among Contents JRR 3 Standard Fucl Elcmcnt(LEU ttel) RR3 Stmdard FucI Element(LEU ttel)

RR 3 Folowcr Typc Fucl Elcmcnt(LEU tte JRR 3 Followcr Typc Fuel Elemcnt(LEU ttcl)

JRR4B Typc Fucl Element(HEU ttcl) Dclcted Aluminium data in thc JRR 4L Type Fuel Element(LEU mcl) Dclettd shielding analysis JRR 4 Fuel Elcmcnt(LEU hc Deleted JMTR Standard Fucl Elcmcnt(LEU Fuel) JMTR Standard Futt Element(LEU Fu )

JMTR Fucl Foliower(LEU Fuel) JMTR Fuel FoIIower(LEU Fucl)

JMTRC Standard Fucl Type A,B,C MTRC Standard FucI Deletcd Elcment(HEU Fucl) Pin Fixing Type B,C Elemcnt(HEU Fucl) Deleted

Special Typc A Spccial Typc A JMTRC Special Fuel JMTRC Spccial Fucl Special Type B Deletcd Elcmcnt(HEU Fuel) Element(HEU Fucl)

Special Typc C,D Dcletcd O Containment ttalysis JMTRC Fucl Fo1lowcr(HEU Fuel) Dclctcd JMTRC Standard Fucl EIemcnt(MEU Fucl) JMTRC Standard Fuel Elemcnt(MEU Fucl)

JMTRC Spccial Fucl Elcmcnt(MEU Fucl) JMTRC Special Fucl Elcmcnt(MEU Fucl)

JMTRC Fuel Followcr(MEU Fuc MTRC Fucl FoIIower(MEU Fue

() Though the registration as contents is delcted,parameter values ofthe fuel element used in the saFety analysis are used as conse at e design values.

The registration as a conte is deleted.Thc parameter vatues of the fuel element used in the safety analysis are taken from those of the MTRC special fuel elemcnt(MEU fuel)and a recalculation has been pcrfo111led.

2.Considerations ofAgin8 0fNuclear Fuel Transport Package ln order to renectthe revisions of Rules on Transponing Nuclcar Fucl Materials etc,outside the Plant or Place of Business"and Notice on the Details of Technicat Standards for Transport of Nuclear Fuel Materials etc.outside he Plant or PIace of Business(fOr thosc effcct e by January l,2021),an eValuation ofthc assumed usage conditions during thc se ice hfe and the subsequent aging was conducted and the results are described in W(II) F.Considerttions ofAging ofNuctear Fuel TranspoH PackageW in Appendix1.

With regard to aging,an evaluation was conducted based on the assumptions ofa 60year se ice life,usage frequency ofthree tinles a year for a transpoi container,and transpohation tilne of 100 days ttthe ma mum pertranspo ion.

Aging factors considered Jbr this transport container were heat,radiation,che lical changes,and fatigue due to repetidve loads,wmlc mate als consttered for aging were stain ss sted, andI .

For mtteri s used for the components of a transpon container(stainttSS steel, and ,assuHing that transpo packages are used 300 days per year for 60 years, even with a conse ative assumption that an neutrons enitted are concentrated in an area ofl cm2 n a COmponent ofatranspon container,the neutron iradiation dose and the absorbed dose are estimated to be in the order of 10H n/cm2 and 102 Gy respectively, which are lower than the ilradiation dose in the order of 1016 n/Cm2 and the absorbed dose of 105 Gy,which are expected to potentiany affect the mechanical properties.

Therefore,there is no impact due to neutron iradiation.

The temperature of the components of a transport container during transportation is assumed

to be 65° C at the maxinlunl,so there is no risk of affecting the lnaterial strength of stainless steel and or the thekkttlal insulation function therefore there is no the 1lal impact.

AInong the lnaterials used fbr the components ofa transport cOntainer,the patts exposed to the air are llnade of stainless steet which fokl Is a paSSive lln on its surface and corosion does not progress easily on it, with an estimated corosion deptt of approximately 60 l for the expected service life,so there is no effect on the sttuctural strength.In addition,the conditions will be checked by a visual examination or others,and they wili be repaired ifnecessary.AIso, because are in a sealed space covered with stainless steel and there is no risk ofcorosion etc.,therc is no impact due to che lical changes, It is assumed that the stainless steel used for the inner container body and the inner container lidwin be suttecttO Changes in intemal pressure duringtransportation,while the stainless steel used for he liting ittings will be subiect tO repetitive loads during handling through the expected service life.As a result ofthe calculation ofthe anowable number of repetitions for these loads,the allowable number of repetitions is well above the estimated totai number of uses.Therefbre,there is no impact due to repetitive loads.

3.Miscellaneous Numbers of f18ures,tables and pages were modined as some of the registered contents were deleted.