ML17201A005

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Rhode Island Nuclear Science Center - Annual Operating Report, Per Technical Specifications 6.7.1
ML17201A005
Person / Time
Site: Rhode Island Atomic Energy Commission
Issue date: 07/19/2017
From: Martin P W
State of RI, Atomic Energy Comm, Nuclear Science Ctr
To: Patrick Boyle
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML17201A005 (20)
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Text

STATEOFRHODEISLANDANDPROVIDENCE PLANTATIONS RhodeIslandAtomicEnergyCommission 16ReactorRoadNarragansett, Rl02882-1165 Telephone

  1. 401-874-2600 July19,2017DocketNo.50-193DocumentControlDesku.s.NuclearRegulatory Commission (NRC)11555Rockville PikeRockville, Maryland20852Attn:Mr.PatrickBoyle,ProjectManager

DearMr.Boyle:

Thisletterandtheenclosures constitute theannualreportrequiredbytheRINSCTechnical Specifications (Section6.7.1).Enclosure 1providesreactoroperating statistics.

Enclosure 2providesinformation pertaining tounscheduled reactorshutdowns orscrams.Enclosure 3discusses maintenance operations performed duringthereporting period.Enclosure 4describes changestothefacilitycarriedoutundertheconditions ofSection50.59ofChapter10oftheCodeofFederalRegulations.

Lastly,Enclosure 5summarizes theradiological controlsinformation.

Ifthereareanyquestions regarding thisinformation, pleasecallmeat401-874-9442.

Sincerely, PaulWMartinJrReactorSupervisor Enclosures (5)Copyto:Mr.CraigBassett,USNRCDr.JohnJ.Breen,Chairman, NRSCDr.ClintonChichester,

Chairman, RIAECDr.NancyBreen,RIAECMr.HowardChun,RIAECDr.YanaK.Reshetnyak, RIAECDr.NitinPadture,RIAEC Enclosure 1ReactorOperating Statistics Technical Specification Section6.7.1.1MonthYearOperating MWHofHoursOperation July201627.5230.33August201632.4731.50September 201626.2824.36October201614.4016.57November201636.0041.02December201630.4537.36January201713.358.42February201752.9554.38March201777.2786.81April2017123.42206.18May2017161.93269.45June2017154.38261.78TotalFY2017750.421068.15MWHor44.51MWDTotalEnergyOutputSinceInitialCriticality 66,785.33 MWHor2782.72MWD ENCLOSURE 2UNSCHEDULED SHUTDOWNS ORSCRAMSTechnical Specification Section6.7.1.2Page1of1Thefollowing isalistoftheunscheduled shutdowns orscramsthatoccurredduringthe2016-2017 reporting period:DateRunLogbookPageCauseDescription No.07/0101691796275WatchdogScrammedtwiceduringstart-upduetocomputerScramcommunication error,hadtorebootcomdeviceonthereactorbridge07/2011691836280Instrumentation ScrammedtwiceduetorangeisolatoroutputforWRchannellbeingirratic.Isolatorwasreplaced.

09/19116920162102OperatorOperatorerrorduringtheperformance ofrodworthtestingwithtrainee.09/22116920262104PowersurgeMomentary lossofpowertoscrammagnetsattributed toACpowerpertibations.

11/03116921262115OperatorAutoscramwhileraisingreactorpower,rangeselection error.02/07117923862148Instrumentation ShortperiodScrampriortoreachingcriticality duetosignalnoise.02/18/17923962149OperatorAutoscramwhilechangingreactoroperating modefortraining.

02/14117924162152Equipment Manuallyscrammedduetoexhaustblowermotorfailurefailure,confmement ventilation inoperable tosupportreactoroperation.

02/16117924462155Instrumentation Scramwhileraisingblade1,noindications, noknowncause.02/211179245631Instrumentation Scramwhileraisingblade3,priortoreachingcriticality duetosignalnoise.03/021179252638Instrumentation Scramwhileraisingblade1,priortoreachingcriticality duetosignalnoise.03/0711792556311Instrumentation Scrampriortoreachingcriticality duetosignalnoise.03/0811792566312Instrumentation ShortperiodScramtwicejustafterreachingcriticality duetosignalnoise.0311611792606317Instrumentation Operatormanuallyscrammedreactorduetoerraticindication onshimsafetyblade#205/0411792876346OperatorOperatorinadvertently initiated amanualrundown.0511711792926352Instrumentation Instrument rack4UPSpertibation causedlossofflowautoscram0511811792936354Instrumentation Instrument rack4UPSfailurecausedlossofflowautoscram0612911793146377Instrumentation Scramwhileraisingblade1,priortoreachingcriticality duetosignalnoise.

ENCLOSURE 3MAINTENANCE OPERATIONS Technical Specification 6.7.1.3requiresalistingofthemajormaintenance operations performed inthe2016-2017 reporting periodincluding theirimpactuponthesafeoperation ofthereactorandthereasonsforthecorrective maintenance.

Thenewstackradiation monitorwasinstalled.

Thenewmonitorisasignificant upgradeandhasthelatesttechnology andfarmorecapabilities thantheoldmonitor.Thecurrentplanisthatitwillbeplacedinserviceastheprimarystackmonitorassoonasithasbeenmadecapableofindicating inthecontrolroomandtheoldmonitorwillcontinuetobemaintained asabackupforaslongasitcontinues toremainfunctional.

TheInletTemperature Scramwasimplemented tocomplywiththenewRINSeTechnical Specifications thatwereapprovedaspartofthere-licensing effort.

ENCLOSURE 4FACILITYCHANGES-10CFR50.59 REVIEWTechnical Specification 6.7.1.4requiresthatweprovidealistinganddescription ofany10CFR50.59evaluations conducted duringthe2016-2017 reporting period.A10CFR50.59evaluation wasperformed onthefollowing facilitychanges:*Newstackradiation monitor*InletTemperature Scramimplemented, OutletTemperature Scrameliminated tocomplywiththenewTSrequirements.

  • AreaRadiation Monitorupgrade.Note:Thisscreenedoutasnoreviewrequired, however,atthelastNRCinspection visit,itwasstronglyrecommended thatwedoareview.Aftercompleting thereview,aconference callwasheldtotrytounderstand whywewereaskedtocompleteareviewonsomething thatclearlyscreenedoutasnoreviewrequired.

Aftercomingtoabetterunderstanding oftheconfiguration andoperation ofourfacility, itwasagreedthatareviewwasnotnecessary orrequired.

Allthreeofthese50.59reviewsareattached.

ENCLOSURE 5RADIOLOGICAL CONTROLS1.Environmental SurveysoutsidetheFacility-Technical Specification 6.7.1.6Quarterly TLD1badgesaredeployedoutsidethereactorbuildinginthreeseparatelocations.

Thequarterly dosesinunitsofmremareshowninthetablebelow.LOCATION3rdQTR4thQTR1stQTR2ndQTR2016201620172017Northeast Wall84a16Demineralizer Door535975390HeatExchanger Door263953171Thegeneralpublicdoesnotfrequenttheselocations andtherefore occupancy factorsmaybeusedtoapproximate annualdose.Theallowable annualexternaldosemustbebelow100mremperyear.Assumingthatthemaximumtimethatamemberofthegeneralpublicwouldbepresentinoneoftheselocations is10minutesperday,anoccupancy factorof0.025canbeusedtoobtaintheannualdosethatwouldbereceivedbyamemberofthegeneralpublic,inanyoftheseareas.TheannualdoseattheNortheast Wall,Demineralizer andHeatExchanger Doorsisdependent ontheoperations scheduleofthereactor.Ignoringthefactthatthedoserateisnotpresent24hoursperday,andapplyingtheoccupancy factorof0.0252,theannualdosethatwouldbereceivebyanindividual inthedemineralizer roomwouldbe14.43mrem.ThedosereceivedattheHeatExchanger Doorwouldbe7.23mrem.TheannualdosereceivedattheNortheast wallwouldbe0.7mrem.Thevariations fromquartertoquarterandfrompreviousreportsarealsodueinparttomovements ofitemswithinthereactorbuildingduringthefiscalyearandvaryinguseofthedifferent irradiation facilities.

2.AnnualExposures Exceeding 500mremforfacilitymembers,100mremfornon-staff membersor10mremformembersofthegeneralpublic-Technical Specification 6.7.1.7Therewerenopersonnel exposures greaterthanTechnical Specification 6.7.1.7.requirements.

lThermoluminescent Dosimeter; MirionTechnology readsthedosimeters atminimumof1mrem.2Occupancy factorwaschangedfrom0.01to0.025.0.01wasderivedusingoccupancy factorandusefactor(itwasassumedthatthereactorisnotrunning8hourseveryday).Wewilluse0.025,fromNCRP147forOutdoors, unattended parkinglots,attics,stairways, unattended elevators, janitor's closets.0.025ismoreconservative numberthan0.01.

3.Radioactive Effluents

-Technical Specification 6.7.1.5A.Individual gaseouseffluentconcentrations foreachreactoroperation arerecordedontheMonthlyInformation Sheets(FormNSC-78).Theconcentration ofradioactive materials intheeffluentreleasedfromthefacilityexhauststacksshallnotexceed1E+05timesconcentrations specified in1OCFR20,AppendixB,TableII,whenaveragedovertimeperiods permitted by1OCFR20.3Gammaspectroscopy ofstackgassampleshasshownthattheprincipal gaseouseffluentisArgon-41.

Themaximumconcentration forthisprinciple contaminant permitted underTechnical Specifications is1E-8IJCi/ccx1E+5=1E-3IJCi/cc.Averageconcentrations releasedduringtheyearwerelessthan0.0683ofthelimit.ThetotalArgon-41releaseduringthereporting periodwas149.54curies.Thecalculated effective doseequivalent forthisreleaseis3mrem/year (COMPLYCode).TheComplyCodereportisattached.

B.Liquideffluentconcentrations releasedtotheenvironment aredocumented ontheSewerDischarge Report(NSC-09).

Eachreleasewasapprovedpriortodischarge withitspHbeingwithintheacceptable rangeandwiththesumofthefractions oftherespective radioisotopes permonthbeingbelowthedischarge limitof1.Forthereporting period,thetotalvolumeofdischarge was1.84E7ml.Theisotopesandtheirrelativeactivities discharged aregivenbelow.Radioisotope TotalActivityDischarged (microcuries)

H-31720.1C-1460.15Pb-2142.86Bi-2145.58K-4034.563Technical Specifications, Section3.7.2.1 Attachment B10CFR50.59ReviewNSC-51Date:Title:1/27/17ApprovedBy:StackMonitorUpgradeMichaelJ.DavisAsanattachment tothisform,provideawrittendescription oftheproposedmodification, thepurposeformakingthemodification, andajustification fortheanswertoeachofthefollowing questions:

1.DoesthechangerequireachangetotheTechnical Specifications oftheR-95License?YNAreviewoftheRINSeTechnical Specifications indicates that:A.Section3.7.1.1Wheneverthefollowing operations areinprogress:

  • Thereactorisoperating.
  • Irradiated fuelhandlingisinprogress.
  • Experiment handlingisinprogressforanexperiment thathasasignificant fissionproduct,orgaseouseffluentactivation productinventory.
  • Anyworkonthecoreorcontrolrodsthatcouldcauseareactivity changeofmorethan0.60%.l\k/kisinprogress.
  • Anyexperiment movementthatcouldcauseareactivity changeofmorethan0.60%.l\k/kisinprogress.

3.7.1.1.1 Aminimumofoneradiation monitorthatiscapableofwarningpersonnel ofhighradiation levelsintheconfinement gaseousandparticulate effluent(Table3.2,RequiredRadiation

Monitors, lines1.1and1.2)shallbeoperating.

3.7.1.1.2 Ifthedetectordescribed inspecification 3.7.1.1.1 failsduringoperation, withinonehour,placeinserviceasuitablealternative airmonitororbeginanhourlygrabsampleanalysis(grabsampleanalysisappliestoparticulate only)inlieuofhavingafunctioning monitor.B.Section3.7.1.23.7.1.2.1 Thestackgaseousmonitorshallalarmwhenradiation levelsofthestackgasare2.5timesnormallevels,orgreater.

3.7.1.2.2 Thestackparticulate monitorshallalarmwhenradiation levelsofthestackparticulates are2timesnormallevels,orgreater.C.Section3.7Table3-2RequiredRadiation Monitors3.2.1RequiredRadiation MonitorsLineDescription MaximumMinimumFunctionOperating

  1. SetPointRequiredMode1.1Confinement 2.5times1Indication andAsperBuildingExhaustnormalalarmboth3.7.1.1.1 StackGaseouslocallyandincontrolroom1.2Confinement 2times1Indication andAsperBuildingExhaustnormalalarmboth3.7.1.1.1 StackParticulate locallyandincontrolroomThenewstackmonitoriscapableoffulfilling allofthemonitoring andalarmcapabilities requiredbytheTechnical Specifications.

Consequently, thischangedoesnotrequireachangetotheTechnical Specifications oftheR-95License.2.Couldthechangeresultinmorethanaminimalincreaseinthefrequency ofoccurrence ofanaccidentthathasbeenpreviously evaluated intheSAR?YNThischangeinvolvesreplacing aradiation monitoring instrument whichisnotassociated withanyofthereactorsafetysystemsanddoesnothaveanyeffectonreactoroperation.

Consequently, thischangewillnotincreasethefrequency ofoccurrence ofanaccidentthathasbeenpreviously evaluated intheSAR.3.Couldthechangeresultinmorethanaminimalincreaseinthelikelihood ofoccurrence ofamalfunction ofastructure, system,orcomponent thatisimportant tosafetyandevaluated intheSAR?YNThischangeinvolvesreplacing aradiation monitoring instrument whichisnotassociated withanyofthereactorsafetysystemsanddoesnothaveanyeffectonreactoroperation.

Consequently, thischangewillnotincreasethelikelihood ofoccurrence ofamalfunction ofastructure, system,orcomponent thatisimportant tosafetyandevaluated intheSAR.4.Couldthechangeresultinmorethanaminimalincreaseintheconsequences ofanaccidentthatisevaluated intheSAR?YNThischangeinvolvesreplacing aradiation monitoring instrument whichisnotassociated withanyofthereactorsafetysystemsanddoesnot haveanyeffectonreactoroperation.

Consequently, thischangewillnotincreasetheconsequences ofanaccidentthatisevaluated intheSAR.5.Couldthechangeresultinmorethanaminimalincreaseintheconsequences ofamalfunction ofastructure, system,orcomponent thatisimportant tosafetyandevaluated intheSAR?YNThischangeinvolvesreplacing aradiation monitoring instrument whichisnotassociated withanyofthereactorsafetysystemsanddoesnothaveanyeffectonreactoroperation.

Consequently, thischangewillnotresultinanincreaseintheconsequences ofamalfunction ofastructure, system,orcomponent thatisimportant tosafetyandevaluated intheSAR.6.Couldthechangeresultincreatingthepossibility ofanaccidentofadifferent typethantheaccidents thathavebeenevaluated intheSAR?yNThischangeinvolvesreplacing aradiation monitoring instrument whichisnotassociated withanyofthereactorsafetysystemsanddoesnothaveanyeffectonreactoroperation.

Consequently, thischangewillnotresultincreatingthepossibility ofanaccidentofadifferent typethantheaccidents thathavebeenevaluated intheSAR.7.Couldthechangeresultincreatingthepossibility foramalfunction ofastructure, system,orcomponent thatisimportant tosafety,withadifferent resultthanpredicted intheSAR?YNThischangeinvolvesreplacing aradiation monitoring instrument whichisnotassociated withanyofthereactorsafetysystemsanddoesnothaveanyeffectonreactoroperation.

Consequently, thischangewillnotresultincreatingthepossibility ofamalfunction ofastructure, system,orcomponent thatisimportant tosafety,withadifferent resultthanpredicted intheSAR.8.Couldthechangeresultinadesignbasislimitforafissionproductbarrierasdescribed intheSARbeingalteredorexceeded?

yNThischangeinvolvesreplacing aradiation monitoring instrument whichisnotpartofanyfissionproductbarrier.Consequently, thischangewillnotresultinadesignbasislimitforafissionproductbarrierasdescribed intheSARbeingalteredorexceeded.

9.Couldthechangeresultinadeparture fromamethodofevaluation usedintheSARforestablishing thedesignbasesforthefacility?

YNThischangeinvolvesreplacing aradiation monitoring instrument whichwasnotusedintheSARasamethodofevaluation forestablishing thedesignbasesforthefacility.

Consequently, thischangewillnotresultin adeparture fromamethodofevaluation usedintheSARforestablishing thedesignbasesforthefacility.

Iftheanswertoanyofthesequestions isyes,thenanNRCapprovedlicenseamendment pursuantto10CFR50.90shallbeobtainedbeforethemodification isimplemented.

Attachment B10CFR50.59ReviewNSC-51Date:Title:3/1/17ApprovedBy:AreaRadiation MonitorUpgradeMichaelJ.DavisAsanattachment tothisform,provideawrittendescription oftheproposedmodification, thepurposeformakingthemodification, andajustification fortheanswertoeachofthefollowing questions:

1.DoesthechangerequireachangetotheTechnical Specifications oftheR-95License?YNAreviewoftheRINSCTechnical Specifications indicates that:A.Section3.7.1.1.3 Thisspecification requiresthataminimumofonegammasensitive radiation monitorthatiscapableofwarningpersonnel ofhighradiation levelsshallbeonthemainflooroftheConfinement Buildingandoverthepoolwhenthereactorisoperating.

Thenewmonitorsarebothgammaandneutronsensitive, andwillbemaintained onthemainfloorandatthepooltop.B.Section3.7.1.2.3 Thisspecification requiresthatthearearadiation monitorsshallalarmwhenradiation levelsare2timesnormallevels,orgreater.Thenewmonitorshavealarmingcapability, andwillbesettoalarmwhenradiation levelsare2timesnormallevels,orgreater.C.Sections4.7.1.1.1 and4.7.1.1.2 Thisspecification requiresthatthearearadiation monitorsonthemainflooroftheConfinement Buildingandoverthepoolareverifiedtobeoperableeachdaypriortothereactorbeingstartedupfromtheshutdowncondition, andafterthechannelhasbeenrepaired.

Thisschedulewillbemaintained.

D.Sections4.7.1.2.1 and4.7.1.2.2 Thisspecification requiresthatthearearadiation monitorsonthemainflooroftheConfinement Buildingandoverthepoolshallbechannelcalibrated andchanneltestedannually.Thisschedule willbemaintained.

Consequently, thischangedoesnotrequireachangetotheTechnical Specifications oftheR-95License.

2.Couldthechangeresultinmorethanaminimalincreaseinthefrequency ofoccurrence ofanaccidentthathasbeenpreviously evaluated intheSAR?YNThischangeinvolvesreplacing radiation monitoring instruments whicharenotassociated withanyofthereactorsafetysystemsanddoesnothaveanyaffectonreactoroperation.

Consequently, thischangewillnotincreasethefrequency ofoccurrence ofanaccidentthathasbeenpreviously evaluated intheSAR.3.Couldthechangeresultinmorethanaminimalincreaseinthelikelihood ofoccurrence ofamalfunction ofastructure, system,orcomponent thatisimportant tosafetyandevaluated intheSAR?YNThischangeinvolvesreplacing radiation monitoring instruments whicharenotassociated withanyofthereactorsafetysystemsanddoesnothaveanyaffectonreactoroperation.

Consequently, thischangewillnotincreasethelikelihood ofoccurrence ofamalfunction ofastructure, system,orcomponent thatisimportant tosafetyandevaluated intheSAR.4.Couldthechangeresultinmorethanaminimalincreaseintheconsequences ofanaccidentthatisevaluated intheSAR?YNThischangeinvolvesreplacing radiation monitoring instruments whicharenotassociated withanyofthereactorsafetysystemsanddoesnothaveanyaffectonreactoroperation.

Consequently, thischangewillnotincreasetheconsequences ofanaccidentthatisevaluated intheSAR.5.Couldthechangeresultinmorethanaminimalincreaseintheconsequences ofamalfunction ofastructure, system,orcomponent thatisimportant tosafetyandevaluated intheSAR?YNThischangeinvolvesreplacing radiation monitoring instruments whicharenotassociated withanyofthereactorsafetysystemsanddoesnothaveanyaffectonreactoroperation.

Consequently, thischangewillnotresultinanincreaseintheconsequences ofamalfunction ofastructure, system,orcomponent thatisimportant tosafetyandevaluated intheSAR.6.Couldthechangeresultincreatingthepossibility ofanaccidentofadifferent typethantheaccidents thathavebeenevaluated intheSAR?YNThischangeinvolvesreplacing radiation monitoring instruments whicharenotassociated withanyofthereactorsafetysystemsanddoesnothaveanyaffectonreactoroperation.

Consequently, thischangewillnotresultincreatingthepossibility ofanaccidentofadifferent typethantheaccidents thathavebeenevaluated intheSAR.

7.Couldthechangeresultincreatingthepossibility foramalfunction ofastructure, system,orcomponent thatisimportant tosafety,withadifferent resultthanpredicted intheSAR?YNThischangeinvolvesreplacing radiation monitoring instruments whicharenotassociated withanyofthereactorsafetysystemsanddoesnothaveanyaffectonreactoroperation.

Consequently, thischangewillnotresultincreatingthepossibility ofamalfunction ofastructure, system,orcomponent thatisimportant tosafety,withadifferent resultthanpredicted intheSAR.8.Couldthechangeresultinadesignbasislimitforafissionproductbarrierasdescribed intheSARbeingalteredorexceeded?

YNThischangeinvolvesreplacing radiation monitoring instruments whicharenotpartofanyfissionproductbarrier.Consequently, thischangewillnotresultinadesignbasislimitforafissionproductbarrierasdescribed intheSARbeingalteredorexceeded.

9.Couldthechangeresultinadeparture fromamethodofevaluation usedintheSARforestablishing thedesignbasesforthefacility?

YNThischangeinvolvesreplacing radiation monitoring instruments whicharenotusedintheSARasamethodofevaluation forestablishing thedesignbasesforthefacility.

Consequently, thischangewillnotresultinadeparture fromamethodofevaluation usedintheSARforestablishing thedesignbasesforthefacility.

Iftheanswertoanyofthesequestions isyes,thenanNRCapprovedlicenseamendment pursuantto10CFR50.90shallbeobtainedbeforethemodification isimplemented.

Attachment B10CFR50.59ReviewNSC-51Date:___------'-1.:.....:/1'-='0.:.....:/1:....:....7 ApprovedBy:MichaelJ.DavisTitle:170110CoolantTemperature ScramSetPointChangeAsanattachment tothisform,provideawrittendescription oftheproposedmodification, thepurposeformakingthemodification, andajustification fortheanswertoeachofthefollowing questions:

1.DoesthechangerequireachangetotheTechnical Specifications oftheR-95License?YNThismodification involvesimplementing achangeinthefacilityTechnical Specifications sothatcoolingsystemtemperature scramsetpointsareconsistent withnewspecifications.

Thenewsettingsare:Indicator FunctionRequiredActualSetPointSetPointPoolTemperature Scram127F126FInletTemperature AlarmNone115FInletTemperature Scram122F119FOutletTemperature AlarmNone126F2.Couldthechangeresultinmorethanaminimalincreaseinthefrequency ofoccurrence ofanaccidentthathasbeenpreviously evaluated intheSAR?YNThismodification hasnoimpactonreactoroperation, oranythingthatcouldcauseanaccident.

Itisstrictlyaslightchangeinthecoolingsystemtemperature alarmandscramsetpoints.3.Couldthechangeresultinmorethanaminimalincreaseinthelikelihood ofoccurrence ofamalfunction ofastructure, system,orcomponent thatisimportant tosafetyandevaluated intheSAR?YNThismodification hasnoimpactontheabilityofthetemperature systemdisplays, andtheirassociated relaysfromfunctioning.

4.Couldthechangeresultinmorethanaminimalincreaseintheconsequences ofanaccidentthatisevaluated intheSAR?YNThenewSafetyAnalysisshowsthatthesechangesintemperature setpointswillhavenosignificant increaseintheconsequences ofanaccidentthathasbeenevaluated intheSAR.

5.Couldthechangeresultinmorethanaminimalincreaseintheconsequences ofamalfunction ofastructure, system,orcomponent thatisimportant tosafetyandevaluated intheSAR?YNThenewSafetyAnalysisshowsthatthesechangesintemperature setpointswillhavenosignificant increaseintheconsequences ofamalfunction ofastructure, system,orcomponent thatisimportant tosafetyandevaluated intheSAR.6.Couldthechangeresultincreatingthepossibility ofanaccidentofadifferent typethantheaccidents thathavebeenevaluated intheSAR?YNThismodification issimplyasetpointchangeandhasnoimpactonanytypeofaccidentotherthanthoseinvolving overheating thefuelcladding, whichhavebeenevaluated intheSAR.7.Couldthechangeresultincreatingthepossibility foramalfunction ofastructure, system,orcomponent thatisimportant tosafety,withadifferent resultthanpredicted intheSAR?YNThismodification hasnoimpactonstructure, system,orcomponent malfunctions.

8.Couldthechangeresultinadesignbasislimitforafissionproductbarrierasdescribed intheSARbeingalteredorexceeded?

yNThismodification hasnoimpactondesignbasislimitsforfissionproductbarriersasdescribed intheSAR.9.Couldthechangeresultinadeparture fromamethodofevaluation usedintheSARforestablishing thedesignbasesforthefacility?YNThismodification cannotresultinadeparture fromamethodofevaluation usedintheSARforestablishing thedesignbasesforthefacility.

Iftheanswertoanyofthesequestions isyes,thenanNRCapprovedlicenseamendment pursuantto10CFR50.90shallbeobtainedbeforethemodification isimplemented.

2017Ar-41releaseCOMPLY:Vl.7.40CFRPart61NationalEmissionStandards forHazardous AirPollutants REPORTONCOMPLIANCE WITH7/12/2017 9:40THECLEANAIRACTLIMITSFORRADIONUCLIDE EMISSIONS FROMTHECOMPLYCODE-Vl.7.Preparedby:RIAtomicEnergyCommission RINuclearScienceCenter16ReactorRoad)Narragansett)

RI02882SanghoNam401-874-2600 Preparedfor:u.S.Environmental Protection AgencyOfficeofRadiation andIndoorAirWashington)

DC20460Page1 2017Ar-41releaseCOMPLY:V1.7.2017Ar-41RealseReportSCREENING LEVEL4DATAENTERED:ReleaseRateNuclide(curies/YEAR)

AR-411.495E+02 Releaseheight35meters.Buildingheight18meters.7/12/2017 9:40Thesourceandreceptorarenotonthesamebuilding.

Buildingwidth18meters.Buildinglength20meters.STACKDISTANCES)

FILE:stackdata100.datDistanceDIR(meters)---------

N100.0NNE100.0NE100.0ENE100.0E100.0Page2 2017Ar-41releaseESE100.0SE100.0SSE100.0S100.0SSW100.0SW100.0WSW100.0W100.0WNW100.0NW100.0NNW100.0COMPLY:V1.7.WINDROSEDATA)FILE:2016windrosedata2m.datSourceofwindrosedata:2016WindrosedataDatesofcoverage:

1954-1994 Windroselocation:

Narragansett)

RIDistancetofacility:

155mPercentcalm:0.05WindSpeedFROMFrequency (meters/s)

N0.0622.00NNE0.0582.00NE0.0442.00ENE0.0132.00E0.0122.00ESE0.0132.00SE0.0582.00SSE0.0492.00S0.0582.00SSW0.0842.00SW0.1052.00WSW0.0642.00W0.0682.00WNW0.0952.00NW0.1042.00NNW0.0682.00DistancefromtheSOURCEtotheFARMproducing VEGETABLES is100meters.Page37/12/2017 9:40 2017Ar-41releaseDistancefromtheSOURCEtotheFARMproducing MILKis100meters.DistancefromtheSOURCEtotheFARMproducing MEATis100meters.NOTES:Thereceptorexposedtothehighestconcentration islocated100.metersfromthesourceintheNEsector.HegetshisVEGETABLES fromafarmlocated100.metersfromthesourceintheNEsector.HegetshisMEATfromafarmlocated100.metersfromthesourceintheNEsector.HegetshisMILKfromafarmlocated100.metersfromthesourceintheNEsector.Inputparameters outsidethe"normal"range:COMPLY:Vl.7.Windrosewindfrequency isunusually LOW.RESULTS:7/12/2017 9:40Effective doseequivalent:

      • Complyatlevel4.ThisfacilityisinCOMPLIANCE.

3.0mrem/yr.ItmayormaynotbeEXEMPTfromreporting totheEPA.YoumaycontactyourregionalEPAofficeformoreinformation.

ENDOFCOMPLIANCE REPORT**********

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