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{{#Wiki_filter:PREPAREDNESS        FORACCIDENT      TOLERANT    FUELLICENSING, INCLUDING    HIGHER    BURNUP  ANDENRICHMENT A Report  forthe Senate  Committee    onAppropriations andthe House  Committee    onAppropriations pS REG(ff DA co                      09 2.
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4AAAC BytheU.S. Nuclear  Regulatory Commission Enclosure
 
Introduction TheU.S.      Nuclear    RegulatoryCommission            (NRC)  developed    this report      asdirected  bythe explanatory    statement    accompanying the          Consolidated  Appropriations      Act,  2021(Public    Law 116-260). The        explanatory    statement      directed  theNRCtoreport      ontheNRC's          preparedness for  licensingthe use of      accidenttolerant      fuel(ATF)  with a focus  onthose        steps  thatarebeing taken  bythestaff to ensure that          theagency    isprepared  toreview    theexpected        licensing requests,    including those for    higher      burnup        andincreased limits,                enrichment        levels.
Applicants    aremovingforward with              plans toseek  approval  tobatch    load'    fuel assemblies    with twoATFtechnologies            (coated    cladding    and doped  p ellets)that mayhave        h igher  burnup  limits andincreased        enrichment      by the mid-2020s.        Theenrichment,    fabrication,      transportation,  and useoftheATFfuel          assembliesrequires NRClicensing            review  andapproval.          TheNRChas already    received    somelicensing        action requests  for theuseofATF,including            higher burnup limits andincreased        enrichment      levels. The current list ofthese  submittals      andtheir  approvals, ifapplicable,    canbefound        ontheNRC's ATF public Webpage(Ref.                  1).
TheNRCstaff          assessed    itsregulatory    framework  andfound    the  existing      regulations  and guidance      aresuitable    for reviews    ofthe  ATFconcepts (i.e.,  coated    cladding      anddoped    pellets) expected      tobesubmitted        inthe  near-term. TheNRC also considers the            existing  regulatory framework      tobegenerally      acceptable      for licensingfuel with increased      enrichment    (from  5to approximately      10percent      uranium-235      byweight)  andhigher fuel    burnup      limits (from 62  to75 gigawatt-days      permetric    tonofuranium        (GWd/MTU),    rodaverage) inthe          near-term. While  the NRC's    existing  regulations    andguidance        support the reviewof ATF licensing actions,          requests for  enrichment      limits higher  than    5 percent  uranium-235  byweight will require license amendments        andexemptions.        TheNRCwill      continue  tolook  forways toenhance the regulatory    framework    through    guidance      andpossible  rulemaking    activities.
TheNRCcompleted            orisperforming        the activitiesdetailed  inthis  report    to support the  NRC's efforts  tocomplete      the  licensing  ofATF,including      higher  burnup  limits    andincreased enrichment,    inparallel    with  theindustry's      research  anddevelopment        efforts  while maintaining reasonable      assurance      ofadequate        protection  ofpublic health  andsafety,        promoting the commondefense          andsecurity,      andprotecting      theenvironment.
Accident      Tolerant    Fuel  Project    Plan While  theNRCisready          toreview      andlicense    ATF,higher    burnup,  andincreased        enrichment submittals    under  the  current  regulatory      framework,  theNRCisalso        taking    steps  tomakeagency processes      moreefficient      andeffective.      TheNRChasdeveloped          theATFProject          Plan (Ref. 2) toprepare      for reviews    ofboth  near-term      andlonger-term    ATFdesigns.        TheProject    Plan, revised    inOctober      2019,  addresses      thecomplete  nuclear  fuelcycle,    including    fuel fabrication, fresh  fuel  transport,  in-reactor  requirements,    andspent    fuel storage    andtransportation.        The NRCstaff      engaged      extensively    with      stakeholders its              inthedevelopment          oftheplan,  including licensees,    nuclear  fuel  vendors,    industry    groups, nongovernmental      organizations,      and international    counterparts,    consistent      with theNRC's    Principles  ofGoodRegulation          and statutory    requirements.
1 A batch  load isthereplacement    ofapproximately            ofthefuel one-third        assembles  inthereactor    coreaftereach operating  cycle.
 
The  Project  Plan outlines  anewapproach        tofuel    licensing inwhich theNRCengages          with applicants    earlierintheir  research  anddevelopment        phase,  inpart toidentify  andresolve potential  safety  issues  promptly. TheProject      Plan  also considers operational    flexibilities that licensees    may  seekbased    uponATFdesigns.          Increased  communication    andengagement occur    onmany fronts, including    routine  vendor    status  meetings,  attendance    atindustry conferences, and a significant increase        inthe    number  andfrequency    ofpresubmittal    meetings.
These    meetings allow the    NRCandstakeholders            toexchange    information  andincrease    the efficiency    ofthereview process. Additionally,theNRCholds              meetings  andissues communications      tofurther support dialogue      with  stakeholders  over specific  technical or administrative    issues.One valuable set      ofmeetings      isheld  monthly with  theU.S. Department ofEnergy      (DOE). Inthese meetings, DOEshares            information onATFstatus      andresearch, which    helps theNRCstaff    toanticipate  what  reviews    maybeneeded.
InApril    2021(Ref. 3), theNRCissued a finalreport          based  upon  information  gathering  activities including,    phenomena    identification  and ranking    tables (PIRT)  and seven    f uelperformance literature  reviews  concerning  near-term ATF concepts, including        spent  fuel transportation  and storage,    andreactor  operating  andaccident conditions. NRC-issued            ATF-related      documents canbefound        ontheNRC's    ATFpublic    Webpage (Ref.4).
TheNRCisalso        developing  orrevising    existing  codes tobeused    for independent      confirmatory calculations. These  confirmatory    calculations    provide insight into fuel andreactor      systems behavior    aswell  aspotential  consequences      oftransient and accident scenarios        andthe identification  ofrisk-significant factors. TheNRCwill        update its codes asdata    andinformation arereceived.
Other    General  Preparatory  Activities TheNRCisactively        involved  intwoElectric    Power    Research  Instituteindustry research frameworks/groups      that arecoordinating    research    onATF,higher    burnup, and increased enrichment      limits.Thefirst  istheCollaborative      Research    onAdvanced      Fuel Technologies (CRAFT)    for  L ight Water  Reactors. Thesecond        is theExtended  Storage  Collaboration Program.      Participation  inboth ofthese    research    frameworks/groups    allows    theNRC tobe better  prepared    toreview  future licensing  submittals    duetoits  heightened  awareness of vendor plans  andresearch    activitiesandprovides      theNRCthe        opportunity tooffer  feedback  to stakeholders    asappropriate.
TheNRCfrequently        interacts  with  international    counterparts  andsubject    matter  experts  through Nuclear    Energy  Agency  (NEA)  working    groups-most        notably  theWorking    Group  on Fuel Safety-and      through international  cooperative    research  programs  toexpand      ourtechnical database    andmaintain    awareness    ofrelevant    policy andtechnical  issues  with  ATF.Some notable    international activitiesinclude:
TheOrganisation    for Economic    Co-operation    andDevelopment      (OECD)/NEA-supported Studsvik  Cladding  Integrity  Project led  byStudsvik    inSweden  hasprovided      data onhigh burnup  fuelandcladding    performance      during  a simulated  loss-of-coolant    accident.
* TheJapan    Atomic  Energy    Agency  hasprovided      data  onchromia    doped  fuel performance  during  a reactivity-initiated    accident  conducted  inits  Nuclear    Safety Research  Reactor.
e    TheNRCstaff      participates  intheCabri      International  Project,led  bytheInstitute    for Radiological  Protection  andNuclear      Safety    inFrance,  which studies    thebehavior    of nuclear  fuelandcladding    during  reactivity-initiated  accidents.
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a  TheNRCstaff          isparticipating    inthe  OECD/NEA's      QUENCH-ATF      project  through  which it obtains data    oncoated      cladding  behavior    indesign-basis  andbeyond-design-basis loss-of-coolant-accident        conditions. TheNRCstaff      isparticipating  intheOECD/NEA Framework        for Irradiation  Experiments    that  waslaunched  tocontinue    the  spiritof international    cooperation    andhighly-leveraged      access  tonuclear  safety,  fuels,and materials    research    that  hasbeenlost    with  the2018closure    oftheHalden      reactor  in Norway.
These international    research    programs      enhance  theNRC's    understanding  ofsafety    significant fuel andthermal-hydraulic system behaviorandprovide                    valuable data  todevelop      andvalidate independent    models    for  the NRC's confirmatory        analysis  codes.
Coated  cladding,    doped    pellets, higher burnup limits,    andincreased    enrichments      levelsare expected  tobethefirst      setoftechnologies submitted toNRCfor            licensing  review. Thenext sections describe    theNRC's      preparations    for each    ofthese  technologies.
Coated  Cladding Nuclear fuel  vendors    arecurrently    researchingand testing fuel      that uses  a zirconium    alloy cladding with  a thin  outer  coating  ofeither  chromium or a proprietary      material. This thincoating isintended  toprovide    resistance    tocorrosion    andwear and additional operational          flexibilityfor power reactors. TheNRChasnotyetreceived                anyin-reactor topical reports    or  license amendment    applications    for batch  loads  ofcoated    cladding but hasactively    engaged    with stakeholders.
TheNRCisprepared          toreview    licensing  submittals    forcoated fuel rod cladding. Togetready, theNRCcontracted        with  nuclear  fuels  experts  from  DOE's  PacificNorthwest    National Laboratory  (PNNL)      toperform    a literature  review  (Ref. 5)ondegradation and failure phenomena related totheATFconcept            ofchromium-coated        fuel  rodcladding  andtoconduct a PlRT exercise onthe    topic. TheNRCthen        published  aninterim  staffguidance  (ISG) on the    subject (Ref.6). This  ISGisavailable      for vendors  toconsult    inpreparing their topical  report submittals, whichshould    help  toreduce    thepotential    for schedule    uncertainty anddelays      caused by submitting  incomplete    documents      for  review.
Withregard  tolicensing      thefront-end    (i.e.,
enrichment,    fuelfabrication, andfresh    fuel transportation)  andtheback-end        fuel  cycle(i.e., spent  fuel transportation andstorage)      for  coated cladding, theNRCstaff        hasreviewed      theapplicable    regulations andguidance      andhasissued twoliterature  reviews    (Refs. 7 and8).      Fromthese    reports,theNRCdetermined          that no additions ormodifications      tothe  front-end  andback-end      regulatory framework      areneeded.
Therefore,  theNRCisprepared            toreview    coated  cladding  front-end andback-end        licensing actionsconsistent    with  theagency's      safety-and-security    mission andinparallel      with the industry's efforts. TheNRChasalready            reviewed    andapproved    twosubmittals      (Refs.9 and10) that allow  fuel  vendors    totransport    fresh  fuel with  coated  cladding.
DopedPellets Fuelvendors    areresearching        andtesting    fuel pellets  thatmixother  materials,  knownas dopants, into  thepellet    during  themanufacturing      process. These  dopants    change    thephysical properties oftheresulting      fuel pellet  with  thegoal    ofproviding  both operational    andaccident condition benefits    for power  reactors.
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The  NRC    hasalready    reviewed    andapproved        twodoped      pellet topical  reports  forboiling water reactor  fuels  (Refs. 11 and  12) and  a license    amendment        (Ref. 13), and  the industry is  currently researching    doped pellets    forpressurized      water    reactor    fuels. Additionally,  thestaff  has reviewed NRC regulations        andguidance        for  the  front-end    andback-end      licensing ofdoped pellets  and determined    that  noadditions      ormodifications        areneeded.      Therefore,  theNRCstaff isprepared    to review pressurized      water    reactor    doped    pellet submittals    anticipated from vendors      Todate, the NRChasreviewed              andapproved          a request  (Ref. 9)that allows  a fuel vendor    totransport fresh fuel    with  doped    pellets.
Higher    Burnup Thecurrent    fuel  burnup  limits differ slightly among        fuel vendors    andfuel    products, but  fuel assemblies    aregenerally    limited to a maximum          rod-average      burnup  of62GWd/MTU.          Thereare potential  applicants  interested  inraising this      limit  toaround    75GWd/MTU        rodaverage. Burnup limits  arenotspecified    inanyregulations, butinsteadareincorporated                    intopower  reactor licenses  onceapproved      intopical    reports. Therefore,      rulemaking    isnotneeded      inthis  areaand thestaff  will only  need to  review  topical  reports    and    license  amendment                in requests to  order approve    increased    burnup  limits.
Thephenomenon          called fuel fragmentation,      relocation,    anddispersal (FFRD)      andits  possible resolutions  areofsignificant    interest  tothe    NRC.FFRD isthe            fragmentation    offuel  pelletsdue toexpanding      fission gasbubbles      under  accident    conditions. Thehigher      theburnup  ofthe  fuel during  accidents,  the smaller  each    fuel  fragment      becomes. These smallerpieces            offuel  may axially  relocate  within thefuel  rodif  therodballoons          outward and may beejected        into  the reactor  coolant  flow  if therodbursts.      Thefuel      vendors    andlicensees mayaddress          FFRDinthe licensing  process    toadopt  higher  burnup    levels  through    modeling. Other possible methods        for addressing    FFRDarecurrently        under    development.          Tobeaware      ofthe progress inboth technical  andlicensing    areas  ofFFRD,theNRCstaff                isencouraging    fuel vendors  tohave preapplication    meetings  ontheir    licensing    approaches        toFFRD,which      three vendors    have done todate. TheNRCstaff      expects    additional  preapplication        meetings  oncevendors have further refined  their  approaches. Additionally,  theNRC's        participation  inCRAFTwill    allow theagency tounderstand      potential applicants'    approaches        tofilling  data  gapsandthenewapproaches to licensing  requests  thatarebeing      developed      for  FFRD.Finally,      theNRCstaff      isdeveloping a research    information  letter thatwill  summarize        theNRCstaff's      understanding    ofavailable research    information  related toFFRDandhowthe                information  canbeused      todefine conservative    limits  fortheextent    offuel  fragmentation        during  a reactor  accident,  the amountof fuel that  could  potentially  bereleased    from    the andthe rod,            impact  offragmentation    onthe release  ofgaseous    radionuclides. TheNRCstaff          currently  plans  toissue  theresearch information  letter  bylate 2021for      usebystakeholders.
Inaddition  totheProject    Plan,  theNRChasproactively              reached    outtopotential    applicants on higher  burnup  limits through  twoNRC-led        public  workshops.      Thefirst,  which  washeld    on July  30,2020,    included  anoverview      ofhigher    burnup    limits  andincreased    enrichment        for levels thepublic  andanexchange        ofinformation      focusing      onthecomponents        ofa quality  submittal.
During  thefollow-up    workshop    onJune10,2021,              theNRCdiscussed        theproposed    research information  letter, the environmental      aspects      ofhigher    burnup  limits, andhigher    burnup  spent fuel storage  andtransportation    issues. These      twoworkshops      provided    a valuable  exchange  of information  with  a variety  ofstakeholders.
TheNRCstaff      hasreviewed    theregulations        andguidance        fortheback-end    licensing  ofhigher burnup  fuel anddetermined      that  noadditions      ormodifications      areneeded.      Therefore,  NRCis 4 -
 
prepared    toreview    these  expected  submittals.      TheNRCdid          notneed    toreview      theregulations and guidance      for the  front-endlicensing  ofhigher      burnup    fuel  because,    from    thefront-end perspective,    higherburnup    fuelisnodifferent      from  other  fuel.
Increased Enrichment Asstated      earlier in this report,the NRCconsiders          theexisting    regulatory    framework      tobe generally    acceptable for licensing fuel    with  increased      enrichment    levels  (from    5  to approximately 10percent      uranium-235    byweight) inthe    near-term      using  license  amendments        andexemptions.
Amendments        would    beneeded tochange      the    enrichment      limit inindividual    licenses,  and exemptions      would  beneeded byeachlicensee            that  wishes  toexceed    the  enrichment    limits in theregulations.
Toefficiently    support    expected requests    for  increased enrichment          levels,  theNRCisexploring theregulatory      options,  includingthepossibility ofinitiating        a rulemaking.      Specifically,  theNRC ispreliminarily    exploring  whether  a rulemaking toamendTitle              10oftheCodeofFederal Regulations    50.68,  "Criticality accident  requirements,"        which  places  anenrichment            of limit 5 percent    onfresh  fuel  orrequires a criticality monitor tobeinuse,would                becost    beneficial.
TheNRCisstill        inthe  earlystages  ofthis  process and will        continue    toexplore      potential regulatory    options  focusing  onenrichments      upto10 percent, which            istherange      ofinterest currently    being  expressed    bypotential  applicants.      Enrichments    upto20percent          mayalso  be given  someconsideration        asthe  staff  looks  atpotentialregulatory changes.Depending                    onthe level ofpreapplication                andother activities          tangible      interest expressed bypotential            applicants, a rulemaking    could  possibly  becompleted    consistent      with  theindustry's plans      toseek    approval  to batch  load    fuel with  increased enrichment    inthe    mid-2020s,      and licensees      could    request exemptions      until thecompletion  oftherulemaking.          TheNRCwillcontinue togauge                interestin pursuing    higher  enrichment  levels andadjust      its efforts    aswarranted.
A keyelement      for  licensing increased  fuel enrichment        levels  willbethe    front-end      ofthefuel cycle. TheNRCstaff        reviewed theregulations        andguidance        forfront-end    licensing  for increased    enrichment    anddetermined    that  noadditions        ormodifications      areneeded. Therefore, theNRCisprepared          toreview  front-end  licensing    actions  for  increased    enrichment levels and hasreviewed      andapproved    several  licensing    actions    that serve  aspreparatory        steps to allow a fuel facility  toachieve    enrichments  above    5weight      percent  (Refs. 15).addition, the 14and            In NRChasissued          oneapproval  (Ref. 9)  that allows    a  fuel  vendor  totransport      fresh  fuelrods with enrichments    above    5 weight  percent  uranium-235.
Toensure      that  potential  applicants understand      theNRC's      timelines  for reviewing      front-end licensing    actions  for increased  enrichments,    theNRCidentified          enrichment      facility        path critical items  for  approving  batch  loadings in2023anddiscussed              themina public        letter totheNuclear Energy    Institute  (Ref. 16).
Iron-Chromium-Aluminum            (FeCrAI)  Cladding      andLonger-Term          Accident      Tolerant  Fuel Concepts TheNRCmonitors          progress  onthe  development        ofFeCrAl      cladding  andlonger-term        ATF concepts. TheNRCstaff      frequently engages      with  DOEandfuel        vendors    tounderstand      the current  status  andfuture    directionofthese    concepts.
TheNRChasnotyetbeenprovided                with  relevant      detailed  schedules,    specific    physical characteristics,    ortechnical  data from  vendors    for  FeCrAl    orother    longer-term    ATFconcepts.
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The  NRC    staff has,  however,    begun  preliminary  research toprepare    forthese    reviews andto determine    whether, andtowhat          extent,  changes    totheexisting  regulatory  framework    maybe needed to license        these ATFtechnologies.        With  uncertainsubmittal  timelines    for these technologies,      itwouldbepremature          for theNRCtoundertake      moreintensive      preparatory activities  at this  time.
Conclusion TheNRCcontinuesto maximize its                preparednesstolicense      near-term  ATFtechnologies (i.e.,coated    cladding    and doped pellets),higher        burnup  limits,andincreased      enrichment  levels, andisprepared        toreviewrequested licensingactions            forbatch  loads. TheNRCwill    continue    to engage    with  potential  applicants,  licensees,  andother  external  stakeholders    toensure  thatthe appropriate    steps    aretaken    sothat ATF, higher      burnup, andincreased    enrichment    licensing reviews    areboth      timely andcomplete, consistent with        maintaining  reasonable      assurance  of adequate      protection  ofpublic    healthand safety, promotingthecommondefense                andsecurity, andprotecting      theenvironment.
References 1        NRCATFPublic          Webpage,      "ATF-relatedLicensing    Actions,"
https://www.nrc.gov/reactors/atf/licensing-actions.html.
: 2.      NRCATFProject            Plan,  Version  1.1,"Project  Planto Prepare the    U.S. Nuclear Regulatory      Commission      for EfficientandEffective  Licensing  ofAccidentTolerant      Fuels,"
October    2019(Agencywide          Documents    Access  andManagement System          (ADAMS)
Accession      No.ML19301B166).
: 3.      NUREG/CR-7283,            ERI/NRC    21-204,  "Phenomena    Identification Ranking Tables      for Accident    Tolerant    Fuel  Designs  Applicable  toSevere  Accident  Conditions,"  preparedfor theU.S. Nuclear    Regulatory    Commission      byEnergy  Research    Inc.,April 2021 (ADAMS Accession      No.ML21113A277).
: 4.      NRCATFPublic          Webpage,        "ATF-related    Documents,"
https://www.nrc.gov/reactors/atf/related-docs.htmi.
: 5.      PNNL-28437,        "Degradation      andFailure    Phenomena    ofAccident    Tolerant  Fuel  Concepts:
Chromium        Coated    zirconium    Alloy Cladding,"  prepared  fortheU.S. Department  of Energy    bythePacific      Northwest    National Laboratory,  January  2019(ADAMS      Accession No.ML19036A716)            andPNNL-28437,        Revision 1,June2019(ADAMS            Accession  No.
19172A154).
: 6.      ATF-ISG-2020-01,          "Supplemental      Guidance  Regarding  theChromium-Coated        zirconium Alloy  Fuel    Cladding  Accident    Tolerant Fuel  Concept," January  2020(ADAMS      Accession No.ML19343A121).
: 7.      PNNL-29773,        "Fresh    Fuel Transportation    ofAccident  Tolerant  Fuel  Concepts  -
Chromium        Coated  zirconium    Alloy Cladding,"  prepared  for theU.S. Department    of Energy    bythePacific      Northwest    National Laboratory,  March  2020(ADAMS        Accession No.ML20134H981).
: 8.      PNNL-30451,        "Spent    Fuel Storage    andTransportation    ofAccident    Tolerant  Fuel Concepts      -
Cr-Coated    zirconium    AlloyandFeCrAl    Cladding,"  prepared    fortheU.S.
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Department      ofEnergy    bythePacific        Northwest    National  Laboratory,  March    2020 (ADAMS Accession        No. ML20274A250).
: 9. Letter  fromJohn    McKirgan,    NRC,toTanya          Sloma,  Westinghouse    Electric  Company, LLC,  "Revision  No.12ofCertificate          ofCompliance      No.9297for      theModel    Nos.
Traveller  STD,  TravellerXL,andTraveller            VVERPackages,"      September    15,2020 (ADAMS      Accession    No.ML20255A297).
: 10. Letter  from  John McKirgan,      NRC,toTimothy          J.Tate,  Framatome      Inc.,"Revision    No.11 ofCertificate    ofCompliance        No.9319,      for  theModel  Nos. MAP-12    andMAP-13 Transportation    Packages,"    January 10,2019        (ADAMS    Package    Accession    No.
ML19011A011).
11  Letter  from  Mirela  Gavrilas, NRC, toJerald          Head,General    Electric-Hitachi,  "Final  Safety Evaluation    for General  Electric  Hitachi    Nuclear  Energy  Americas,    LLCTopical    Report NEDC-33406P,        Revision  2,'Additive FuelPellets        ForGNFFuel        Designs'  (TAC No.ME3082)"      November    9,2015(ADAMS PackageAccession                    No.ML15195A459).
: 12. ANP-10340P-A,        Revision  0,Incorporation ofChromia-Doped              Fuel  Properties    inAREVA Approved    Methods,"  Framatome        Inc., May 2018 (ADAMS Accession            No.
ML18171A119).
: 13. Letter  from  Andrew  Hon,NRC,toJohn            A.Krakuszeski,    DukeEnergy      Progress,    LLC, "Brunswick    Steam  Electric  Plant,    Units  1and2 Issuance ofAmendment Nos.
299and 327toRevise      Technical  Specification      5.6.5b  toAllowApplication ofAdvanced Framatome      Atrium  11Fuel    Methodologies        (EPID  L-2018-LLA-0273),"      March    6,2020 (ADAMS    Accession    No.ML20073F186).
: 14. Letter  from  Jacob  zimmerman,      NRCtoWyatt          Padgett,  Louisiana Energy Services LLC, "U.S. Louisiana  Energy  Services    -
Amendment        85,Change    toLicense Condition 6band Enrichment    Limit  (Enterprise    Project  Identification  Number    L-2019-LLA-0264),"      May19, 2020(ADAMS        Package    Accession    No.ML20119A040).
: 15. Letter  from  Tyrone  D.Naquin,      NRC,toScott        P.Murray,  Global  Nuclear  Fuels-America, "Global  Nuclear  FuelAmericas LLC:Review        oftheMinimum      Margin  ofSubcriticality for upto8 Weight      Percent  Enrichment        ofUranium-235    andAmendment        16(Enterprise Project  Identifier L-2020-LNS-0002),"        August    13,2020(ADAMS        Package    AccessionNo.
ML20219A463).
: 16. Letter  from  Kathryn  M.Brock,      NRC,toJanet        R.Schlueter,  Nuclear    Energy  Institute, "Preparing    for EfficientandEffective        Licensing  ofAccident    Tolerant  Fuel  with  Higher Enrichment,"    August  26,2019(ADAMS              Package    Accession    No.ML19235A261).
7 -}}

Revision as of 15:07, 17 January 2022

Preparedness for Accident Tolerant Fuel Licensing, Including Higher Burnup and Enrichment - a Report for the Senate Committee on Appropriations and the House Committee on Appropriations Enclosure
ML21130A363
Person / Time
Issue date: 06/25/2021
From: Christopher Hanson
NRC/Chairman
To: Delauro R, Leahy P
US Congress, US HR (House of Representatives), US SEN (Senate)
Orenak M
Shared Package
ML21155A171 List:
References
CORR-21-0043, SRM-OGC201228-2
Download: ML21130A363 (8)
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