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| {{#Wiki_filter:UNITEDSTATESOFAlVKRICANUCLEARREGULATORYCOMMSSIONIntheMatterofRochesterGasandElectricCorporation(R.E.GinnaNuclearPowerPlant))))DocketNo.50-244)APPLICATIONFORAMENDMENTTPERATLIEKPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(NRC),RochesterGasandElectricCorporation(RG8cE),holderofFacilityOperatingLicense¹.DPR-18,herebyrequeststhattheTechnicalSpecificationssetforthinAppendixA,tothatlicense,beamended.ThisrequestforchangeistocorrectthespecifiedaccumulatorboratedwatervolumevaluesinSR3.5.1.2tomatchtheassociatedaccumulatorpercentlevelvalues.Adescriptionoftheamendmentrequest,necessarybackgroundinformation,justificationoftherequestedchanges,anosignificanthazardsandenvironmentalconsiderationsareprovidedinAttachmentI.Thisevaluationdemonstratesthattheproposedchangesdonotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeftluentsoranychangeintheauthorizedpowerlevelofthefacility.Theproposedchangesalsodonotinvolveasignificanthazardsconsideration.9708270i989708i9]PORADOCK05000244PPDR AmarkedupcopyoftheGinnaStationTechnicalSpecificationswhichshowtherequestedchangesissetforthinAttachmentII.TheproposedrevisedtechnicalspecificationsareprovidedinAttachmentIII.WHEREFORE,ApplicantrespectfullyrequeststhatFacilityOperatingLicenseNo.DPR-18,andAttachmentAtothatlicense,beamendedintheformattachedheretoasAttachmentIII.RochesterGasandElectricCorporationByRobertC.MecreyVicePresidentNuclearOperationsSubscribedandsworntobeforemeonthis19thdayofAugust1997.NotaryPublicDEBORAHA.PIPERNINotaryPublicmtheStateofNewYorkONTARIOCOUNTYCommissionCxpiresNov.23,19,.7.7. | | {{#Wiki_filter:UNITEDSTATESOFAlVKRICANUCLEARREGULATORY COMMSSION IntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant))))DocketNo.50-244)APPLICATION FORAMENDMENT TPERATLIEKPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (NRC),Rochester GasandElectricCorporation (RG8cE),holderofFacilityOperating License¹.DPR-18,herebyrequeststhattheTechnical Specifications setforthinAppendixA,tothatlicense,beamended.Thisrequestforchangeistocorrectthespecified accumulator boratedwatervolumevaluesinSR3.5.1.2tomatchtheassociated accumulator percentlevelvalues.Adescription oftheamendment request,necessary background information, justification oftherequested changes,anosignificant hazardsandenvironmental considerations areprovidedinAttachment I.Thisevaluation demonstrates thattheproposedchangesdonotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeftluents oranychangeintheauthorized powerlevelofthefacility. |
| AttachmentIR.E.GinnaNuclearPowerPlantLicenseAmendmentRequestCorrectionofAccumulatorBoratedWaterVolume(SR3.5.1.2)Thisattachmentprovidesadescriptionofthelicenseamendmentrequest(LAR)andthenecessaryjustificationstosupportcorrectionoftheaccumulatorboratedwatervolumesspecifiedinSR3.5.1.2.Thisattachmentisdividedintosixsectionsasfollows.SectionAsummarizesallchangestotheGinnaStationImprovedTechnicalSpecifications(ITS)whileSectionBprovidesthebackgroundandhistoryassociatedwiththechangesbeingrequested.SectionCprovidesthejustificationsassociatedwiththeseproposedchanges.AnosignificanthazardsconsiderationevaluationandenvironmentalconsiderationoftherequestedchangestotheGinnaStationTechnicalSpecificationsareprovidedinSectionsDandE,respectively.SectionFlistsallreferencesusedinthisattachment.A.DESCRIPTIONOFTECHNICALSPECIFICATIONCHANGESThisLARproposestorevisetheGinnaStationITSassummarizedbelowandshowninAttachmentII.1.LCO3.5.1SR3.5.1.2isrevisedtocorrectthespecifiedaccumulatorboratedwatervolumevaluesinordertomatchwiththeassociatedaccumulatorpercentlevelvalues.B.BACKGROUNDOnFebruary13,1996,theNRCissuedAmendmentNo.61totheGinnaStationtechnicalspecifications.ThisamendmentreplacedtheexistingGinnaStationtechnicalspecificationsintheirentiretywithITSthatwerebasedonNUREG-1431.IncludedwithintheITSwastheadditionofspecificaccumulatorboratedwatervolumestomatchwiththeexistingaccumulatorpercentlevelvalues.Thatis,theprevioustechnicalspecificationsalreadyrequiredanaccumulatorinventorybasedonpercentlevel.ThewatervolumesincubicfeetthatwereaddedtoSR3.5.2.1wereintendedtobethesameaccumulatorinventoriesandwerethosecalledoutintheaccidentanalyses.However,asidentifiedinRG&EActionReport97-0960,ithassincebeendeterminedthatthewatervolumesasspecifiedintheITSdonotcorrectlymatchupwiththepercentlevelvalues.Thiswasduetoanerrorintheaccumulatorwallthicknessusedinthecalculation.
| | Theproposedchangesalsodonotinvolveasignificant hazardsconsideration. |
| ToensurecontinuedcompliancewiththeexistingSR3.5.2.1requirements,RG8'cEiscurrentlymaintainingRWSTlevelbetween67%and82%level(versusthespecified50%to82%level).Thisbandwasdeterminedbasedonmeetingthemostlimitingofthespecifiedcubicfeetandpercentlevelvalues.RG&EandWestinghousehavesincere-evaluatedtheaffectedaccidentanalyses(e.g.,smallandlargeLOCAandsteamlinebreaks)usingthecorrectcubicfeetvalueswithrespecttothe50%and82%levelsasspecifiedinSR3.5.2.1anddeterminedanegligiblechangeresults(i.e.,theresultsareacceptable).ItshouldbenotedthatasdescribedonITSbasespageB3.5-4,onlyanominalaccumulatorlevelisusedintheaccidentanalysisduetocompetingeffectsofhigherversuslowerlevels.Thatis,theaccidentanalysisdoesnotusetheupperandloweraccumulatorvolumes,onlyanaverage.Consequently,thepurposeofthisLARistocorrecttheconversionerror.NomodificationsarerequiredinordertoimplementthisLAR.C.JUSTIFICATIONOFCHANGESThissectionprovidesthejustificationforallchangesdescribedinSectionAaboveandshowninAttachmentII.Thejustificationsareorganizedbasedonwhetherthechangeis:morerestrictive(M),lessrestrictive(L),administrative(A),ortherequirementisrelocated(R).Thejustificationslistedbelowarealsoreferencedinthetechnicalspecification(s)whichareaffected(seeAttachmentII).ItisnotedthatthereareonlyadministrativechangesassociatedwiththisLAR.C.1miniraiv1.TheaccumulatorboratedwatervolumeincubicfeetiscorrectedinordertomatchwiththespecifiedaccumulatorpercentlevelinSR3.5.2.1.Thischangeisrequiredtocorrectanerrorthatwascausedbyusinganincorrectaccumulatorwallthickness.Theaffectedaccidentanalyses(e.g.,smallandlargeLOCAandsteamlinebreaks)havebeenre-evaluatedbyRG&;EandWestinghouseusingthecorrectcubicfeetvalueswithrespecttothe50%and82%levels.Theresultsindicatethattherewasanegligliblechangesuchthatallrequirementswithrespecttotheemergencycorecoolingsystemremainmet(e.g.,10CFR50,AppendixK).Therearenotlessrestrictive(L),morerestrictive(M),orrelocated(R)changesassociatedwiththisLAR.
| | 9708270i98 9708i9]PORADOCK05000244PPDR AmarkedupcopyoftheGinnaStationTechnical Specifications whichshowtherequested changesissetforthinAttachment II.Theproposedrevisedtechnical specifications areprovidedinAttachment III.WHEREFORE, Applicant respectfully requeststhatFacilityOperating LicenseNo.DPR-18,andAttachment Atothatlicense,beamendedintheformattachedheretoasAttachment III.Rochester GasandElectricCorporation ByRobertC.MecreyVicePresident NuclearOperations Subscribed andsworntobeforemeonthis19thdayofAugust1997.NotaryPublicDEBORAHA.PIPERNI NotaryPublicmtheStateofNewYorkONTARIOCOUNTYCommission CxpiresNov.23,19,.7.7. |
| D.SIGNIFICANTHAZARDSCONSIDERATIONEVALUATIONTheproposedchangestotheGinnaStationTechnicalSpecificationsasidentifiedinSectionAandjustifiedinSectionChavebeenevaluatedwithrespectto,10CFR50.92(c)andshowntonotinvolveasignificanthazardsconsiderationasdescribedbelow.ThissectionisorganizedbasedonSectionCabove.D.1linfminirihnTheadministrativechangesdiscussedinSectionC.ldonotinvolveasignificanthazardsconsiderationasdiscussedbelow:OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.Thechangeisonlytocorrectaconversionerrorwithrespecttoaccumulatorboratedwatervolume.Thisdoesnotincreasetheprobabilityofanyaccidentpreviouslyevaluatedsincetheaccumulatorwatervolumeprovidesmitigationcapabilityonly(i.e.,doesnotinitiateanyaccident).Theaffectedaccidentanalyseswithrespecttotheaccumulator(e.g.,smallandlargeLOCAandsteamlinebreak)havebeenre-evaluatedusingthecorrectaccumulatorwatervolumevalueswithacceptableresults.Therefore,thesechangesdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Theproposedchangesdonotinvolveaphysicalalterationoftheplant(i.e.,nonewordifferenttypeofequipmentwillbeinstalled)orchangesinthemethodsgoverningnormalplantoperation.GinnaStationoperatorsverifyaccumulatorwatervolumeviapercentlevel(versuscubicfeet)whichremainsunchanged.Thus,thischangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantreductioninamarginofsafety.Theproposedchangesonlycorrectaconversionerror.Theerrorhasbeenre-evaluatedwithacceptableresults.Assuch,noquestionofsafetyisinvolved,andthechangedoesnotinvolveasignificantreductioninamarginofsafety.Basedupontheaboveinformation,ithasbeendeterminedthattheproposedchangestotheGinnaStationTechnicalSpecificationsdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,doesnotcreatethepossibilityofanewordifferentkindofaccidentpreviouslyevaluated,anddoesnotinvolveasignificantreductioninamarginofsafety.Therefore,itisconcludedthattheproposedchangesmeettherequirementsof10CFR50.92(c)anddonotinvolveasignificanthazardsconsideration. | | Attachment IR.E.GinnaNuclearPowerPlantLicenseAmendment RequestCorrection ofAccumulator BoratedWaterVolume(SR3.5.1.2)Thisattachment providesadescription ofthelicenseamendment request(LAR)andthenecessary justifications tosupportcorrection oftheaccumulator boratedwatervolumesspecified inSR3.5.1.2.Thisattachment isdividedintosixsectionsasfollows.SectionAsummarizes allchangestotheGinnaStationImprovedTechnical Specifications (ITS)whileSectionBprovidesthebackground andhistoryassociated withthechangesbeingrequested. |
| E.ENVIRONMENTALCONSIDERATIONRGBhasevaluatedtheproposedchangesanddeterminedthat:1.ThechangesdonotinvolveasignificanthazardsconsiderationasdocumentedinSectionDabove;2.Thechangesdonotinvolveasignificantchangeinthetypesorsignificantincreaseintheamountsofanyeftluentsthatmaybereleasedoffsitesincenospecificationsrelatedtooffsitereleasesareaffected;and3.ThechangesdonotinvolveasignificantincreaseinindividualorcumulativeoccupationalradiationexposuresincenonewordifferenttypeofequipmentarerequiredtobeinstalledasaresultofthisLAR.Accordingly,theproposedchangesmeettheeligibilitycriteriaforcategoricalexclusionsetforthin10CFR51.22(c)(9).Therefore,pursuantto10CFR51.22(b),anenvironmentalassessmentoftheproposedchangesisnotrequired.F.REFERENCESNone.}} | | SectionCprovidesthejustifications associated withtheseproposedchanges.Anosignificant hazardsconsideration evaluation andenvironmental consideration oftherequested changestotheGinnaStationTechnical Specifications areprovidedinSectionsDandE,respectively. |
| | SectionFlistsallreferences usedinthisattachment. |
| | A.DESCRIPTION OFTECHNICAL SPECIFICATION CHANGESThisLARproposestorevisetheGinnaStationITSassummarized belowandshowninAttachment II.1.LCO3.5.1SR3.5.1.2isrevisedtocorrectthespecified accumulator boratedwatervolumevaluesinordertomatchwiththeassociated accumulator percentlevelvalues.B.BACKGROUND OnFebruary13,1996,theNRCissuedAmendment No.61totheGinnaStationtechnical specifications. |
| | Thisamendment replacedtheexistingGinnaStationtechnical specifications intheirentiretywithITSthatwerebasedonNUREG-1431. |
| | IncludedwithintheITSwastheadditionofspecificaccumulator boratedwatervolumestomatchwiththeexistingaccumulator percentlevelvalues.Thatis,theprevioustechnical specifications alreadyrequiredanaccumulator inventory basedonpercentlevel.ThewatervolumesincubicfeetthatwereaddedtoSR3.5.2.1wereintendedtobethesameaccumulator inventories andwerethosecalledoutintheaccidentanalyses. |
| | However,asidentified inRG&EActionReport97-0960,ithassincebeendetermined thatthewatervolumesasspecified intheITSdonotcorrectly matchupwiththepercentlevelvalues.Thiswasduetoanerrorintheaccumulator wallthickness usedinthecalculation. |
| | Toensurecontinued compliance withtheexistingSR3.5.2.1requirements, RG8'cEiscurrently maintaining RWSTlevelbetween67%and82%level(versusthespecified 50%to82%level).Thisbandwasdetermined basedonmeetingthemostlimitingofthespecified cubicfeetandpercentlevelvalues.RG&EandWestinghouse havesincere-evaluated theaffectedaccidentanalyses(e.g.,smallandlargeLOCAandsteamlinebreaks)usingthecorrectcubicfeetvalueswithrespecttothe50%and82%levelsasspecified inSR3.5.2.1anddetermined anegligible changeresults(i.e.,theresultsareacceptable). |
| | Itshouldbenotedthatasdescribed onITSbasespageB3.5-4,onlyanominalaccumulator levelisusedintheaccidentanalysisduetocompeting effectsofhigherversuslowerlevels.Thatis,theaccidentanalysisdoesnotusetheupperandloweraccumulator volumes,onlyanaverage.Consequently, thepurposeofthisLARistocorrecttheconversion error.Nomodifications arerequiredinordertoimplement thisLAR.C.JUSTIFICATION OFCHANGESThissectionprovidesthejustification forallchangesdescribed inSectionAaboveandshowninAttachment II.Thejustifications areorganized basedonwhetherthechangeis:morerestrictive (M),lessrestrictive (L),administrative (A),ortherequirement isrelocated (R).Thejustifications listedbelowarealsoreferenced inthetechnical specification(s) whichareaffected(seeAttachment II).Itisnotedthatthereareonlyadministrative changesassociated withthisLAR.C.1miniraiv1.Theaccumulator boratedwatervolumeincubicfeetiscorrected inordertomatchwiththespecified accumulator percentlevelinSR3.5.2.1.Thischangeisrequiredtocorrectanerrorthatwascausedbyusinganincorrect accumulator wallthickness. |
| | Theaffectedaccidentanalyses(e.g.,smallandlargeLOCAandsteamlinebreaks)havebeenre-evaluated byRG&;EandWestinghouse usingthecorrectcubicfeetvalueswithrespecttothe50%and82%levels.Theresultsindicatethattherewasanegliglible changesuchthatallrequirements withrespecttotheemergency corecoolingsystemremainmet(e.g.,10CFR50,AppendixK).Therearenotlessrestrictive (L),morerestrictive (M),orrelocated (R)changesassociated withthisLAR. |
| | D.SIGNIFICANT HAZARDSCONSIDERATION EVALUATION TheproposedchangestotheGinnaStationTechnical Specifications asidentified inSectionAandjustified inSectionChavebeenevaluated withrespectto,10CFR50.92(c)andshowntonotinvolveasignificant hazardsconsideration asdescribed below.Thissectionisorganized basedonSectionCabove.D.1linfminirihnTheadministrative changesdiscussed inSectionC.ldonotinvolveasignificant hazardsconsideration asdiscussed below:Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated. |
| | Thechangeisonlytocorrectaconversion errorwithrespecttoaccumulator boratedwatervolume.Thisdoesnotincreasetheprobability ofanyaccidentpreviously evaluated sincetheaccumulator watervolumeprovidesmitigation capability only(i.e.,doesnotinitiateanyaccident). |
| | Theaffectedaccidentanalyseswithrespecttotheaccumulator (e.g.,smallandlargeLOCAandsteamlinebreak)havebeenre-evaluated usingthecorrectaccumulator watervolumevalueswithacceptable results.Therefore, thesechangesdonotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously analyzed. |
| | Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated. |
| | Theproposedchangesdonotinvolveaphysicalalteration oftheplant(i.e.,nonewordifferent typeofequipment willbeinstalled) orchangesinthemethodsgoverning normalplantoperation. |
| | GinnaStationoperators verifyaccumulator watervolumeviapercentlevel(versuscubicfeet)whichremainsunchanged. |
| | Thus,thischangedoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated. |
| | Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant reduction inamarginofsafety.Theproposedchangesonlycorrectaconversion error.Theerrorhasbeenre-evaluated withacceptable results.Assuch,noquestionofsafetyisinvolved, andthechangedoesnotinvolveasignificant reduction inamarginofsafety.Basedupontheaboveinformation, ithasbeendetermined thattheproposedchangestotheGinnaStationTechnical Specifications donotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, doesnotcreatethepossibility ofanewordifferent kindofaccidentpreviously evaluated, anddoesnotinvolveasignificant reduction inamarginofsafety.Therefore, itisconcluded thattheproposedchangesmeettherequirements of10CFR50.92(c)anddonotinvolveasignificant hazardsconsideration. |
| | E.ENVIRONMENTAL CONSIDERATION RGBhasevaluated theproposedchangesanddetermined that:1.Thechangesdonotinvolveasignificant hazardsconsideration asdocumented inSectionDabove;2.Thechangesdonotinvolveasignificant changeinthetypesorsignificant increaseintheamountsofanyeftluents thatmaybereleasedoffsitesincenospecifications relatedtooffsitereleasesareaffected; and3.Thechangesdonotinvolveasignificant increaseinindividual orcumulative occupational radiation exposuresincenonewordifferent typeofequipment arerequiredtobeinstalled asaresultofthisLAR.Accordingly, theproposedchangesmeettheeligibility criteriaforcategorical exclusion setforthin10CFR51.22(c)(9). |
| | Therefore, pursuantto10CFR51.22(b), |
| | anenvironmental assessment oftheproposedchangesisnotrequired. |
| | F.REFERENCES None.}} |
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ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17265A6921999-06-28028 June 1999 Application for Amend to License DPR-18 to Revise ITS Associated with RCS Leakage Detection Instrumentation.Lar Proposed as Result of Commitment That Rg&E Submit as Part of Staff Review of Application of leak-before-break Status ML17265A5691999-03-0101 March 1999 Application for Amend to License DPR-18,proposing Change in ITS to Revise Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A4651998-11-24024 November 1998 Application for Amend to License DPR-18,revising Improved Tech Spec Description of Fuel Cladding Matl (TS 4.2.1) & Updating References Provided in TS 5.6.5 for COLR ML17265A2431998-04-27027 April 1998 Application for Amend to License DPR-18,revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17264B0431997-09-29029 September 1997 Application for Amend to License DPR-18,revising Administrative Controls W/Respect to RCS Pressure & Temp Limits Rept ML17264B0381997-09-29029 September 1997 Application for Amend to License DPR-18,revising TS Re Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Revised Setpoint Analysis ML17264B0021997-08-19019 August 1997 Application for Amend to License DPR-18,allowing Testing of Certain ECCS motor-operated Valves in Mode 4 Which Currently Requires Entry in LCO 3.0.3 ML17264A9981997-08-19019 August 1997 Application for Amend to License DPR-18,correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A8661997-04-24024 April 1997 Application for Amend to License DPR-18,revising RCP PT & Administrative Control Requirements ML17264A8471997-03-31031 March 1997 Application for Amend to License DPR-18,revising Spent Fuel Pool Storage Requirements ML20134D9911996-10-29029 October 1996 Application for Amend to License DPR-18,requesting Change to Mode of Applicability for Auxiliary Feedwater Pump Actuation on Main Feedwater Pump ML17264A7121996-10-29029 October 1996 Application for Amend to License DPR-18 Requesting Change to Required Actions for Inoperable Channels Associated with Auxiliary Feedwater Pump ML17264A5991996-09-13013 September 1996 Application for Amend to License DPR-18,revising RCS Pressure & Temp Limits Rept ML17264A4701996-05-0808 May 1996 Application for Amend to License DPR-18,correcting Typos ML17264A4041996-03-15015 March 1996 Application for Amend to License DPR-18,revising TS to Incorporate Methodology for Determining RCS P/T Limits & LTOP Limits in Administrative Controls Section of RCS P/T Limits Rept ML17264A3441996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS Table 3.3.2-1,Function 5b, Feedwater Isolation,Sg Water Level - High to Raise Allowable Value & Trip Setpoint ML17264A3381996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS to Incorporate Ref to Methodology for Determining LTOP Limits Into Administrative Controls Section for RCS PT Limits Rept ML17264A3331996-02-0909 February 1996 Application for Amend to License DPR-18,revising Requirements for Containment Closure During Mode 6 to Allow Use of Installed Overhead Door Assembly to Isolate Equipment Hatch Opening ML17264A3221996-01-26026 January 1996 Application for Amend to License DPR-18,incorporating Changes Necessary to Reflect Revised Nuclear Fuel Loading ML17264A2521995-11-27027 November 1995 Application for Amend to License DPR-18,revising TS to Implement 10CFR50,App J,Option B ML17264A2551995-11-20020 November 1995 Application for Amend to License DPR-18,submitting Changes to TS Instrumentation Requirements & Conversion to Improved TS ML17264A1501995-08-31031 August 1995 Application for Amend to License DPR-18,proposing Ts,By Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS ML17263B0671995-05-26026 May 1995 Application for Amend to License DPR-18,revising TSs in Entirety to Convert to Improved TSs ML17263A9771995-03-13013 March 1995 Application for Amend to License DPR-18,to Revise TS 4.4.2.4.a to Replace Specific Leakage Testing Frequencies for Containment Isolation Valves ML17309A5501994-07-15015 July 1994 Application for Amend to License DPR-18,proposing TS 3.5, Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431 ML17263A7141994-06-24024 June 1994 Application for Amend to License DPR-18,re Upgrading of Administrative Controls Section 6 ML17263A7071994-06-15015 June 1994 Notarized Application for Amend to License DPR-18 Re Reactor Coolant Activity ML17263A6551994-05-23023 May 1994 Application for Amend to License DPR-18,increasing Allowable Reactor Coolant Activity Levels to Improved TS (NUREG-1431) ML17263A6411994-05-13013 May 1994 Application for Amend to License DPR-18,revising TS Administrative Controls Section 6.0 Consistent W/Improved TS ML17263A3181993-07-13013 July 1993 Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS ML17263A2081993-04-0505 April 1993 Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR ML17262B1171992-12-17017 December 1992 Application for Amend to License DPR-19,revising TS Sections 3.2 & 3.3 to Eliminate Use of High Concentration Boric Acid as safety-related Source of SI Pumps & Increasing Allowable Outage Times ML17262B0991992-11-30030 November 1992 Application for Amend to License DPR-18,revising TS to Remove Table of Containment Isolation Valves & Provide Ref in Bases to UFSAR ML17262B0571992-10-0808 October 1992 Corrected Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Consisting of Notarized Page Two ML17262B0431992-10-0808 October 1992 Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Per Guidance Provided in GL 91-11 Re Resolution of GI 48 ML17262B0201992-09-15015 September 1992 Application for Amend to License DPR-18,revising TS Sections 3.1.1.4,3.1.1.6,4.3.4 & Adding site-specific Basis Sections to Address GL 90-06 Re Resolution of Generic Issues 70 & 94 ML17262A9121992-06-22022 June 1992 Application for Amend to License DPR-18,revising TS 4.3.1 Per Guidance Provided in Generic Ltr 91-01, Removal of Schedule for Withdrawal of Reactor Vessel Matl Specimens from Ts. ML17262A8311992-04-23023 April 1992 Application for Amend to License DPR-18,changing TSs to Redefine Snubber Visual Insp Schedule,Per Generic Ltr 90-09 Guidance ML17262A8211992-04-21021 April 1992 Application for Amend to License DPR-18,instituting Std License Condition for Fire Protection Program & Removing Requirements for Fire Protection Sys from Tss,Per Guidance in Generic Ltrs 86-10 & 88-12 ML17262A7861992-03-23023 March 1992 Application for Amend to License DPR-18,revising Tech Spec Section 6.5.1, Plant Operations Review Committee Function. ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] |
Text
UNITEDSTATESOFAlVKRICANUCLEARREGULATORY COMMSSION IntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant))))DocketNo.50-244)APPLICATION FORAMENDMENT TPERATLIEKPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (NRC),Rochester GasandElectricCorporation (RG8cE),holderofFacilityOperating License¹.DPR-18,herebyrequeststhattheTechnical Specifications setforthinAppendixA,tothatlicense,beamended.Thisrequestforchangeistocorrectthespecified accumulator boratedwatervolumevaluesinSR3.5.1.2tomatchtheassociated accumulator percentlevelvalues.Adescription oftheamendment request,necessary background information, justification oftherequested changes,anosignificant hazardsandenvironmental considerations areprovidedinAttachment I.Thisevaluation demonstrates thattheproposedchangesdonotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeftluents oranychangeintheauthorized powerlevelofthefacility.
Theproposedchangesalsodonotinvolveasignificant hazardsconsideration.
9708270i98 9708i9]PORADOCK05000244PPDR AmarkedupcopyoftheGinnaStationTechnical Specifications whichshowtherequested changesissetforthinAttachment II.Theproposedrevisedtechnical specifications areprovidedinAttachment III.WHEREFORE, Applicant respectfully requeststhatFacilityOperating LicenseNo.DPR-18,andAttachment Atothatlicense,beamendedintheformattachedheretoasAttachment III.Rochester GasandElectricCorporation ByRobertC.MecreyVicePresident NuclearOperations Subscribed andsworntobeforemeonthis19thdayofAugust1997.NotaryPublicDEBORAHA.PIPERNI NotaryPublicmtheStateofNewYorkONTARIOCOUNTYCommission CxpiresNov.23,19,.7.7.
Attachment IR.E.GinnaNuclearPowerPlantLicenseAmendment RequestCorrection ofAccumulator BoratedWaterVolume(SR3.5.1.2)Thisattachment providesadescription ofthelicenseamendment request(LAR)andthenecessary justifications tosupportcorrection oftheaccumulator boratedwatervolumesspecified inSR3.5.1.2.Thisattachment isdividedintosixsectionsasfollows.SectionAsummarizes allchangestotheGinnaStationImprovedTechnical Specifications (ITS)whileSectionBprovidesthebackground andhistoryassociated withthechangesbeingrequested.
SectionCprovidesthejustifications associated withtheseproposedchanges.Anosignificant hazardsconsideration evaluation andenvironmental consideration oftherequested changestotheGinnaStationTechnical Specifications areprovidedinSectionsDandE,respectively.
SectionFlistsallreferences usedinthisattachment.
A.DESCRIPTION OFTECHNICAL SPECIFICATION CHANGESThisLARproposestorevisetheGinnaStationITSassummarized belowandshowninAttachment II.1.LCO3.5.1SR3.5.1.2isrevisedtocorrectthespecified accumulator boratedwatervolumevaluesinordertomatchwiththeassociated accumulator percentlevelvalues.B.BACKGROUND OnFebruary13,1996,theNRCissuedAmendment No.61totheGinnaStationtechnical specifications.
Thisamendment replacedtheexistingGinnaStationtechnical specifications intheirentiretywithITSthatwerebasedonNUREG-1431.
IncludedwithintheITSwastheadditionofspecificaccumulator boratedwatervolumestomatchwiththeexistingaccumulator percentlevelvalues.Thatis,theprevioustechnical specifications alreadyrequiredanaccumulator inventory basedonpercentlevel.ThewatervolumesincubicfeetthatwereaddedtoSR3.5.2.1wereintendedtobethesameaccumulator inventories andwerethosecalledoutintheaccidentanalyses.
However,asidentified inRG&EActionReport97-0960,ithassincebeendetermined thatthewatervolumesasspecified intheITSdonotcorrectly matchupwiththepercentlevelvalues.Thiswasduetoanerrorintheaccumulator wallthickness usedinthecalculation.
Toensurecontinued compliance withtheexistingSR3.5.2.1requirements, RG8'cEiscurrently maintaining RWSTlevelbetween67%and82%level(versusthespecified 50%to82%level).Thisbandwasdetermined basedonmeetingthemostlimitingofthespecified cubicfeetandpercentlevelvalues.RG&EandWestinghouse havesincere-evaluated theaffectedaccidentanalyses(e.g.,smallandlargeLOCAandsteamlinebreaks)usingthecorrectcubicfeetvalueswithrespecttothe50%and82%levelsasspecified inSR3.5.2.1anddetermined anegligible changeresults(i.e.,theresultsareacceptable).
Itshouldbenotedthatasdescribed onITSbasespageB3.5-4,onlyanominalaccumulator levelisusedintheaccidentanalysisduetocompeting effectsofhigherversuslowerlevels.Thatis,theaccidentanalysisdoesnotusetheupperandloweraccumulator volumes,onlyanaverage.Consequently, thepurposeofthisLARistocorrecttheconversion error.Nomodifications arerequiredinordertoimplement thisLAR.C.JUSTIFICATION OFCHANGESThissectionprovidesthejustification forallchangesdescribed inSectionAaboveandshowninAttachment II.Thejustifications areorganized basedonwhetherthechangeis:morerestrictive (M),lessrestrictive (L),administrative (A),ortherequirement isrelocated (R).Thejustifications listedbelowarealsoreferenced inthetechnical specification(s) whichareaffected(seeAttachment II).Itisnotedthatthereareonlyadministrative changesassociated withthisLAR.C.1miniraiv1.Theaccumulator boratedwatervolumeincubicfeetiscorrected inordertomatchwiththespecified accumulator percentlevelinSR3.5.2.1.Thischangeisrequiredtocorrectanerrorthatwascausedbyusinganincorrect accumulator wallthickness.
Theaffectedaccidentanalyses(e.g.,smallandlargeLOCAandsteamlinebreaks)havebeenre-evaluated byRG&;EandWestinghouse usingthecorrectcubicfeetvalueswithrespecttothe50%and82%levels.Theresultsindicatethattherewasanegliglible changesuchthatallrequirements withrespecttotheemergency corecoolingsystemremainmet(e.g.,10CFR50,AppendixK).Therearenotlessrestrictive (L),morerestrictive (M),orrelocated (R)changesassociated withthisLAR.
D.SIGNIFICANT HAZARDSCONSIDERATION EVALUATION TheproposedchangestotheGinnaStationTechnical Specifications asidentified inSectionAandjustified inSectionChavebeenevaluated withrespectto,10CFR50.92(c)andshowntonotinvolveasignificant hazardsconsideration asdescribed below.Thissectionisorganized basedonSectionCabove.D.1linfminirihnTheadministrative changesdiscussed inSectionC.ldonotinvolveasignificant hazardsconsideration asdiscussed below:Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
Thechangeisonlytocorrectaconversion errorwithrespecttoaccumulator boratedwatervolume.Thisdoesnotincreasetheprobability ofanyaccidentpreviously evaluated sincetheaccumulator watervolumeprovidesmitigation capability only(i.e.,doesnotinitiateanyaccident).
Theaffectedaccidentanalyseswithrespecttotheaccumulator (e.g.,smallandlargeLOCAandsteamlinebreak)havebeenre-evaluated usingthecorrectaccumulator watervolumevalueswithacceptable results.Therefore, thesechangesdonotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously analyzed.
Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Theproposedchangesdonotinvolveaphysicalalteration oftheplant(i.e.,nonewordifferent typeofequipment willbeinstalled) orchangesinthemethodsgoverning normalplantoperation.
GinnaStationoperators verifyaccumulator watervolumeviapercentlevel(versuscubicfeet)whichremainsunchanged.
Thus,thischangedoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant reduction inamarginofsafety.Theproposedchangesonlycorrectaconversion error.Theerrorhasbeenre-evaluated withacceptable results.Assuch,noquestionofsafetyisinvolved, andthechangedoesnotinvolveasignificant reduction inamarginofsafety.Basedupontheaboveinformation, ithasbeendetermined thattheproposedchangestotheGinnaStationTechnical Specifications donotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, doesnotcreatethepossibility ofanewordifferent kindofaccidentpreviously evaluated, anddoesnotinvolveasignificant reduction inamarginofsafety.Therefore, itisconcluded thattheproposedchangesmeettherequirements of10CFR50.92(c)anddonotinvolveasignificant hazardsconsideration.
E.ENVIRONMENTAL CONSIDERATION RGBhasevaluated theproposedchangesanddetermined that:1.Thechangesdonotinvolveasignificant hazardsconsideration asdocumented inSectionDabove;2.Thechangesdonotinvolveasignificant changeinthetypesorsignificant increaseintheamountsofanyeftluents thatmaybereleasedoffsitesincenospecifications relatedtooffsitereleasesareaffected; and3.Thechangesdonotinvolveasignificant increaseinindividual orcumulative occupational radiation exposuresincenonewordifferent typeofequipment arerequiredtobeinstalled asaresultofthisLAR.Accordingly, theproposedchangesmeettheeligibility criteriaforcategorical exclusion setforthin10CFR51.22(c)(9).
Therefore, pursuantto10CFR51.22(b),
anenvironmental assessment oftheproposedchangesisnotrequired.
F.REFERENCES None.