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

Out l i ne of Desi gn Approval f or Nucl ear Fuel Transport Package usi ng Type RF-90Y950K Transpoi Col l t ai ner Out hne Thi s t ranspon cont ai ner has been used t o t ranspoA new t t el s f or research react ors f rom France and ot her count ri es si nce 1991( t he 01dest one was manuFact ured i n 1991), and t O t ransport i ow i l radi at ed f uel s t o t he. S,, vhi l e t aki ng necessary hcensi ng procedures such as havi ng peri odi ca y

renewed t he approval peri od and havi ng appl i ed f or approval amendment f br addi t i on of cont ent s

( Spent f ue Wi t h domest i c adopt i on of t he 2018 edi t i on of I AEA``Regul at i ons f or t he Saf e Transpo of Radi oact i ve Mt t eri al, "t he rcgul at i ons i nct udi ng t hosc known f or O si t e Transport Regul at i ons were revi sed on J anuary l, 2021 t o add consi derat i ons of agi ng duri ng st oragc 6f t ranspon cont ai ners and duri ng use of nuct ear f uel t ranspon package( st at uS Wi t h cont ent s i oaded i n a t ransport cont ai ner). I n accordance wi t h t hi s revi si on, we have deci ded t o add a descri pt i on of t he resui t s of consi derat i ons and eval ut t i ons of agi ng i n he at t achment whi ch expl ai ns saf et y( an i t em t o be dcscri bed i n an at t achment ) and t O del et e t he regi st ered cont ent s whi ch wi l l not be t ransponed i n f ut ure and appl y f or t he regi st rat i on. I n addi t i on, i t was deci ded t hat t hi s apphcat i on was t o be submi t t ed as a new appl i ct t i on( appl i Cat i on f or desi gn approval ) i n acCOrdmcc wi t h t he sui dance f rom t hc Nucl ear Re8ul at i on Aut horl t y.

The del et i on of regi st ered cont ent s and t he agi ng cf f cct s do not need t o be consi dercd i n conf l kl i l i ng comphancevi t h t he t echni cal cri t eri a, and t heref ore t he resul t s of t hese saf et y anal yses

( St ruCt ural anal yds, t herrnal anal yds, se h8 anys, shemhg anal ySi s, and cri t i ci t y andys) remal n unchanged.

1. Del et i on of regi st ered cont ent s wi t hout a pl an of t ransport at i on i n t he f ut ure Curent Cont ent s( 16 t ypes)

Cont ent s i n Fut ure( 8 t ypes)

Largest among Cont ent s J RR 3 St andard Fucl El cmcnt ( LEU t t el )

RR-3 St mdard FucI El ement ( LEU t t el )

RR 3 Fol owcr Typc Fucl El cmcnt ( LEU t t e J RR 3 Fol l owcr Typc Fuel El emcnt ( LEU t t cl )

J RR-4B Typc Fucl El ement ( HEU t t cl )

Dcl ct ed J RR 4L Type Fuel El ement ( LEU mcl )

Dcl et t d

Al umi ni um dat a i n t hc shi el di ng anal ysi s J RR 4 Fuel El cmcnt ( LEU hc Del et ed J MTR St andard Fucl El cmcnt ( LEU Fuel )

J MTR St andard Fut t El ement ( LEU Fu)

J MTR Fucl Fol i ower( LEU Fuel )

J MTR Fuel FoI I ower( LEU Fucl )

J MTRC St andard Fucl El cment ( HEU Fucl )

Type A, B, C MTRC St andard FucI El emcnt ( HEU Fucl )

Del et cd Pi n Fi xi ng Type B, C Del et ed

J MTRC Speci al Fuel El cmcnt ( HEU Fuel )

Speci al Typc A J MTRC Spcci al Fucl El ement ( HEU Fucl )

Spcci al Typc A Speci al Type B Del et cd Speci al Typc C, D Dcl et cd O Cont ai nment t t al ysi s J MTRC Fucl Fo1l owcr( HEU Fuel )

Dcl ct cd J MTRC St andard Fucl EI emcnt ( MEU Fucl )

J MTRC St andard Fuel El emcnt ( MEU Fucl )

J MTRC Spcci al Fucl El cmcnt ( MEU Fucl )

J MTRC Speci al Fucl El cmcnt ( MEU Fucl )

J MTRC Fuel Fol l owcr( MEU Fuc MTRC Fucl FoI I ower( MEU Fue

( ) Though t he regi st rat i on as cont ent s i s del ct ed, paramet er val ues of t he f uel el ement used i n t he saFet y anal ysi s are used as conseat e desi gn val ues.

The regi st rat i on as a cont e i s del et ed. Thc paramet er vat ues of t he f uel el ement used i n t he saf et y anal ysi s are t aken f rom t hose of t heMTRC speci al f uel el emcnt ( MEU f uel ) and a recal cul at i on has been pcrf o111l ed.

2. Consi derat i ons of Agi n8 0f Nucl ear Fuel Transport Package l n order t o renect t he revi si ons of Rul es on Transponi ng Nucl car Fucl Mat eri al s et c, out si de t he Pl ant or Pl ace of Busi ness"and Not i ce on t he Det ai l s of Techni cat St andards f or Transport of Nucl ear Fuel Mat eri al s et c. out si de he Pl ant or PI ace of Busi ness' ' ( f Or t hosc ef f cct e by J anuary l, 2021), an eVal uat i on of t hc assumed usage condi t i ons duri ng t hc se i ce hf e and t he subsequent agi ng was conduct ed and t he resul t s are descri bed i n W( I I )

F. Consi dert t i ons of Agi ng of Nuct ear Fuel TranspoH PackageW i n Appendi x-1.

Wi t h regard t o agi ng, an eval uat i on was conduct ed based on t he assumpt i ons of a 60- year se i ce l i f e, usage f requency of t hree t i nl es a year f or a t ranspoi cont ai ner, and t ranspohat i on t i l ne of 100 days t t t he mamum pert ranspoi on.

Agi ng f act ors consi dered J br t hi s t ransport cont ai ner were heat, radi at i on, che l i cal changes, and f at i gue due t o repet i dve l oads, wml c mat eal s const t ered f or agi ng were st ai nss st ed, andI For mt t eri s used f or t he component s of a t ranspon cont ai ner( st ai nt t SS st eel,

and, assuHi ng t hat t ranspo packages are used 300 days per year f or 60 years, even wi t h a conseat i ve assumpt i on t hat an neut rons eni t t ed are concent rat ed i n an area of l cm2 n a COmponent of at ranspon cont ai ner, t he neut ron i radi at i on dose and t he absorbed dose are est i mat ed t o be i n t he order of 10H n/cm2 and 102 Gy respect i vel y, whi ch are l ower t han t he i l radi at i on dose i n t he order of 1016 n/Cm2 and t he absorbed dose of 105 Gy, whi ch are expect ed t o pot ent i any af f ect t he mechani cal propert i es.

Theref ore, t here i s no i mpact due t o neut ron i radi at i on.

The t emperat ure of t he component s of a t ransport cont ai ner duri ng t ransport at i on i s assumed

t o be 65° C at t he maxi nl unl, so t here i s no ri sk of af f ect i ng t he l nat eri al st rengt h of st ai nl ess st eel and or t he t hekkt t l al i nsul at i on f unct i on t here i s no t he1l al i mpact.

AI nong t he l nat eri al s used f br t he component s of a t ransport cOnt ai ner, t he pat t s exposed t o t he ai r are l l nade of st ai nl ess st eet whi ch f okl I s a paSSi ve l l n on i t s surf ace and corosi on does not progress easi l y on i t, wi t h an est i mat ed corosi on dept t of approxi mat el y 60 l f or t he expect ed servi ce l i f e, so t here i s no ef f ect on t he st t uct ural st rengt h. I n addi t i on, t he condi t i ons wi l l be checked by a vi sual exami nat i on or ot hers, and t hey wi l i be repai red i f necessary. AI so, because are i n a seal ed space covered wi t h st ai nl ess st eel and t here i s no ri sk of corosi on et c., t herc i s no i mpact due t o chel i cal changes,

I t i s assumed t hat t he st ai nl ess st eel used f or t he i nner cont ai ner body and t he i nner cont ai ner l i dwi n be sut t ect t O Changes i n i nt emal pressure duri ngt ransport at i on, whi l e t he st ai nl ess st eel used f or he l i t i ng i t t i ngs wi l l be subi ect t O repet i t i ve l oads duri ng handl i ng t hrough t he expect ed servi ce l i f e. As a resul t of t he cal cul at i on of t he anowabl e number of repet i t i ons f or t hese l oads, t he al l owabl e number of repet i t i ons i s wel l above t he est i mat ed t ot ai number of uses. Theref bre, t here i s no i mpact due t o repet i t i ve l oads.

3. Mi scel l aneous Numbers of f 18ures, t abl es and pages were modi ned as some of t he regi st ered cont ent s were del et ed.

t heref ore