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| {{#Wiki_filter:Attachment;ARemove3.1-4b3.1-4e3.5-3Insert3;1-4b3.1-4e3.1-4f3.5-38401250282840119,',"PDRADQCK05000244.,'"".PDR 3.1.1.5PressurizerWheneverthereactorisathotshutdownorcriticalthepressurizershallhaveatleast100kwofheatersoperableandawaterlevelmaintainedbetween10.6%and87%oflevelspan.Ifthepressurizerisinoperableduetoheaterorwaterlevel,restorethepressurizertooperablestatuswithin6hrs.orhavetheRHRsysteminoperationwithinanadditional6hrs.,Bases:TheplantisdesignedtooperatewithallreactorcoolantloopsinoperationandmaintaintheDNBRabove1.30duringallnormal3.1-4bChangeNo.ggAmendmentNo.gP,gg,jfg>PROPOSED TemperaturerequirementsforthesteamgeneratorcorrespondwithmeasuredNDTfortheshellandallowablethermalstressesinthetubesheet.Eachofthepressurizercodesafetyvalvesisdesignedtorelieve288,000lbs.perhr.ofsaturatedsteamatthevalvesetpoint.Below350Fand350psiginthereactorcoolantsystem,the0residualheatremovalsystemcanremovedecayheatandtherebyIIcontrolsyst'mtemperatureandpressure.Ifnoresidualheatwereremovedbyanyofthemeansavailable,theamountofsteamwhichcouldbegeneratedatsafetyvalvereliefpressurewouldbelessthanhalfthevalves'apacity.Onevalve,therefore,providesadequatedefenseagainstoverpressurization.Thepoweroperatedreliefvalves(PORVs)operatetorelieveRCSpressurebelowthesettingofthepressurizercodesafetyvalves.Thesereliefvalveshaveremotelyoperatedblockvalvestoprovideapositiveshutoffcapabilityshouldareliefvalvebecomeinoper-able.TheelectricalpowerforboththereliefvalvesandtheblockvalvesiscapableofbeingsuppliedfromanemergencypowersourcetoensuretheabilitytosealthispossibleRCSleakagepath.Therequirementthat100kwofpressurizerheatersandtheirassociatedcontrolsbecapableofbeingsuppliedelectricalpowerfromanemergencybusprovidesassurancethattheseheaterscanbeenergizedduring''ossofoffsitepowerconditiontomaintainnaturalcirculationathotshutdownandduring3.1-4eAmendmentNo.gP,gg,PROPOSED cooldown.Thepressurizerlowlevellimitof10.6%is"the(3)levelbelowwhichtheheatersarede-energizedtopreventdamage.References(1)FSARSection14.1.6(2)FSARSection7.2.3(3)LetterfromL.D.White,Jr.toD.L.Ziemann,USNRC,datedOctober17,19793.1-4fPROPOSED TABLE3.5-1INSTRUMENTOPERATIONCONDITIONSPage1of2NO.FUNCTIONALUNITNO.ofMIN.MIN.NO.ofCHANNELSOPERABLEDEGREEOFCHANNELSTOTRIP***CHANNELS'REDUNDANCYPERMISSIBLEBYPASSCGNDITIONS6OPERATORACTIONIFCONDITIONSOFCOLUMN3OR5CANNOTBEMET1.Manual2.NuclearFluxPowerRangelowsettinghighsetting3.NuclearFluxIntermediateRange222of4pawerrangechannelsgreaterthan8%F.P.(lawsettingonly)2of4powerrangechannelsgreaterthan8%F.P.MaintainhotshutdawnMaintainhotshutdawnMaintainhotshutdawn.Note14.NuclearFluxSourceRange5.OvertemperatureT1of2intermediateMaintainhotrangechygnelsgreatershutdown.Notethan10amps.=1Maintainhotshutdown6.Overpawer-TCOs7OQMgU~8.HiPressurizerPressureZawPressurizerPressureMaintainhotshutdawnMaintainhotshutdownMaintainhotshutdownPressurizer-HiWaterLevelMaintainhotshutdawnLawFlowinoneloop(>50%F.P.)LowFlowbothloops(10-50%F.P.)3/loop2/loop(anyloop)3/loop2/loop(anyloop)MaintainhotshutdownMaintainhotshutdown AttachmentBThecurrentspecificationonpressurizerwaterlevelstatesthatthepressurizerlevelshallbemaintainedbetween12and87%.Theupperlimitisbasedonahighleveltripsetpointwithsufficientmargintoaccountforreferencelegheatup.Thereisnobasisforthe12%lowerlimit.Sincelowpressurizerheatersarede-energizedat10.6%,amoreappropriatevaluewouldbe10.6%.TheP-10permissiveallowsmanualblockingoftheinter-mediaterangerodstop,theintermediaterangehighfluxtrip,andlowsetpointofthepowerrangehighfluxtripabove10%power.Thesetripsareusedtomitigatetheconsequencesofarodwith-drawaltransientfromsubcritical.TheproposedTechnicalSpecificationchangewouldallowtheabovetripstobebypassed(blocked)at8%power.ThischangeisnecessarybecauseP-7permissiveisrequiredat8.5%power.SinceoneoftheinputstoP-7comesfromthesamepowerrangebistablethatsuppliesP-10,P-10mustbeactuatedat8%powertosatisfy'.therequirementsforP-7.P-7automaticallyunblocksthefollow-.ingreactortrips:2looplowflow,reactorcoolantpumpbusundervoltage,reactorcoolantpumpbusunderfrequency,pressurizerlowpressure,andturbinetripwithP-9.Thesetripsareassociatedwiththe130MWwhichistheupperlimitofheatremovalwhileonnaturalcirculation.Theonlytransientanalysiswhichusesthistripisaslowrodwithdrawal.(Borondilutionisboundedbytheslowrodwithdrawal.)TheonlyeffectofreducingP-10to8%wouldbethatarodwithdrawalaccident(RWA)startingfrom8%wouldbeterminatedbyhighfluxandovertemperatureTversustheintermediateandreducedhighpowertrips.AnevaluationperformedontheRWAstartingfrom8%and10%forvariousreactivityinsertionratesshowsapproximatelythesameDNBRwhentheRWAisinitiatedfrom8%versus10%power.Further,thereissubstantialmarginbetweentheDNBRforaRWAfrom10%andthelimitingRWAfrom100%power.TheDNBRforaRWAstartingfrom8%willalsobegreaterthantheDNBRforthelimitingRWAstartedfrom100%power.Therefore,reducingP-10to8%hasnegligibleeffectontheGinnaSafetyAnalysisandtheminimumDNBRforall..RWAsisunchanged. | | {{#Wiki_filter:Attachment; ARemove3.1-4b3.1-4e3.5-3Insert3;1-4b3.1-4e3.1-4f3.5-38401250282840119,'," |
| AttachmentCInaccordancewith10CFR50.91,thesechangestotheTechnicalSpecificationshavebeenevaluatedagainstthreecriteriatodetermineiftheoperationofthefac'ilityinaccordancewiththeproposedamendmentwould:l.involveasignificant,increaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated;or2.createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated;or3.involveasignificantreductioninamarginofsafety.Asoutlinedbelow,RochesterGasandElectricsubmitsthattheissuesassociatedwiththisamendmentrequestareoutsidethecriteriaof10CFR50.91,andtherefore,anosignificanthazardsfindingiswarranted.Theproposedchangewouldreducethelowerpressurizerlevel'.limitfrom12to10.6%.Thisdoesnotincreasetheprobabilityo'consequencesofanaccident.Thisdoesnotcreateanewordifferentaccident.Thisdoesnotreduceasafetymargin.TheproposedchangealsoreducestheP-10setpointfrom10to8%.Theevaluationdoneshowsthatforthelimitingaccidents,thesafetymarginisnotsignificantlyreduced.Thischangedoesnotincreasetheprobabilityorconsequencesofanaccident.Thischangesdoesnotcreateanewordifferentaccident.Therefore,anosignificanthazardsfindingiswarrantedfortheproposedchanges.
| | PDRADQCK05000244.,' |
| | "".PDR 3.1.1.5Pressurizer Wheneverthereactorisathotshutdownorcriticalthepressurizer shallhaveatleast100kwofheatersoperableandawaterlevelmaintained between10.6%and87%oflevelspan.Ifthepressurizer isinoperable duetoheaterorwaterlevel,restorethepressurizer tooperablestatuswithin6hrs.orhavetheRHRsysteminoperation withinanadditional 6hrs.,Bases:Theplantisdesignedtooperatewithallreactorcoolantloopsinoperation andmaintaintheDNBRabove1.30duringallnormal3.1-4bChangeNo.ggAmendment No.gP,gg,jfg>PROPOSED Temperature requirements forthesteamgenerator correspond withmeasuredNDTfortheshellandallowable thermalstressesinthetubesheet.Eachofthepressurizer codesafetyvalvesisdesignedtorelieve288,000lbs.perhr.ofsaturated steamatthevalvesetpoint. |
| | Below350Fand350psiginthereactorcoolantsystem,the0residualheatremovalsystemcanremovedecayheatandtherebyIIcontrolsyst'mtemperature andpressure. |
| | Ifnoresidualheatwereremovedbyanyofthemeansavailable, theamountofsteamwhichcouldbegenerated atsafetyvalvereliefpressurewouldbelessthanhalfthevalves'apacity. |
| | Onevalve,therefore, providesadequatedefenseagainstoverpressurization. |
| | Thepoweroperatedreliefvalves(PORVs)operatetorelieveRCSpressurebelowthesettingofthepressurizer codesafetyvalves.Thesereliefvalveshaveremotelyoperatedblockvalvestoprovideapositiveshutoffcapability shouldareliefvalvebecomeinoper-able.Theelectrical powerforboththereliefvalvesandtheblockvalvesiscapableofbeingsuppliedfromanemergency powersourcetoensuretheabilitytosealthispossibleRCSleakagepath.Therequirement that100kwofpressurizer heatersandtheirassociated controlsbecapableofbeingsuppliedelectrical powerfromanemergency busprovidesassurance thattheseheaterscanbeenergized during''oss ofoffsitepowercondition tomaintainnaturalcirculation athotshutdownandduring3.1-4eAmendment No.gP,gg,PROPOSED cooldown. |
| | Thepressurizer lowlevellimitof10.6%is"the(3)levelbelowwhichtheheatersarede-energized topreventdamage.References (1)FSARSection14.1.6(2)FSARSection7.2.3(3)LetterfromL.D.White,Jr.toD.L.Ziemann,USNRC,datedOctober17,19793.1-4fPROPOSED TABLE3.5-1INSTRUMENT OPERATION CONDITIONS Page1of2NO.FUNCTIONAL UNITNO.ofMIN.MIN.NO.ofCHANNELSOPERABLEDEGREEOFCHANNELSTOTRIP***CHANNELS'REDUNDANCY PERMISSIBLE BYPASSCGNDITIONS 6OPERATORACTIONIFCONDITIONS OFCOLUMN3OR5CANNOTBEMET1.Manual2.NuclearFluxPowerRangelowsettinghighsetting3.NuclearFluxIntermediate Range222of4pawerrangechannelsgreaterthan8%F.P.(lawsettingonly)2of4powerrangechannelsgreaterthan8%F.P.MaintainhotshutdawnMaintainhotshutdawnMaintainhotshutdawn. |
| | Note14.NuclearFluxSourceRange5.Overtemperature T1of2intermediate Maintainhotrangechygnelsgreatershutdown. |
| | Notethan10amps.=1Maintainhotshutdown6.Overpawer |
| | -TCOs7OQMgU~8.HiPressurizer PressureZawPressurizer PressureMaintainhotshutdawnMaintainhotshutdownMaintainhotshutdownPressurizer-Hi WaterLevelMaintainhotshutdawnLawFlowinoneloop(>50%F.P.)LowFlowbothloops(10-50%F.P.)3/loop2/loop(anyloop)3/loop2/loop(anyloop)MaintainhotshutdownMaintainhotshutdown Attachment BThecurrentspecification onpressurizer waterlevelstatesthatthepressurizer levelshallbemaintained between12and87%.Theupperlimitisbasedonahighleveltripsetpointwithsufficient margintoaccountforreference legheatup.Thereisnobasisforthe12%lowerlimit.Sincelowpressurizer heatersarede-energized at10.6%,amoreappropriate valuewouldbe10.6%.TheP-10permissive allowsmanualblockingoftheinter-mediaterangerodstop,theintermediate rangehighfluxtrip,andlowsetpointofthepowerrangehighfluxtripabove10%power.Thesetripsareusedtomitigatetheconsequences ofarodwith-drawaltransient fromsubcritical. |
| | TheproposedTechnical Specification changewouldallowtheabovetripstobebypassed(blocked) at8%power.Thischangeisnecessary becauseP-7permissive isrequiredat8.5%power.SinceoneoftheinputstoP-7comesfromthesamepowerrangebistablethatsuppliesP-10,P-10mustbeactuatedat8%powertosatisfy'. |
| | therequirements forP-7.P-7automatically unblocksthefollow-.ingreactortrips:2looplowflow,reactorcoolantpumpbusundervoltage, reactorcoolantpumpbusunderfrequency, pressurizer lowpressure, andturbinetripwithP-9.Thesetripsareassociated withthe130MWwhichistheupperlimitofheatremovalwhileonnaturalcirculation. |
| | Theonlytransient analysiswhichusesthistripisaslowrodwithdrawal. |
| | (Borondilutionisboundedbytheslowrodwithdrawal.) |
| | TheonlyeffectofreducingP-10to8%wouldbethatarodwithdrawal accident(RWA)startingfrom8%wouldbeterminated byhighfluxandovertemperature Tversustheintermediate andreducedhighpowertrips.Anevaluation performed ontheRWAstartingfrom8%and10%forvariousreactivity insertion ratesshowsapproximately thesameDNBRwhentheRWAisinitiated from8%versus10%power.Further,thereissubstantial marginbetweentheDNBRforaRWAfrom10%andthelimitingRWAfrom100%power.TheDNBRforaRWAstartingfrom8%willalsobegreaterthantheDNBRforthelimitingRWAstartedfrom100%power.Therefore, reducingP-10to8%hasnegligible effectontheGinnaSafetyAnalysisandtheminimumDNBRforall..RWAsisunchanged. |
| | Attachment CInaccordance with10CFR50.91,thesechangestotheTechnical Specifications havebeenevaluated againstthreecriteriatodetermine iftheoperation ofthefac'ility inaccordance withtheproposedamendment would:l.involveasignificant, increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated; or3.involveasignificant reduction inamarginofsafety.Asoutlinedbelow,Rochester GasandElectricsubmitsthattheissuesassociated withthisamendment requestareoutsidethecriteriaof10CFR50.91,andtherefore, anosignificant hazardsfindingiswarranted. |
| | Theproposedchangewouldreducethelowerpressurizer level'.limitfrom12to10.6%.Thisdoesnotincreasetheprobability o'consequences ofanaccident. |
| | Thisdoesnotcreateanewordifferent accident. |
| | Thisdoesnotreduceasafetymargin.TheproposedchangealsoreducestheP-10setpointfrom10to8%.Theevaluation doneshowsthatforthelimitingaccidents, thesafetymarginisnotsignificantly reduced.Thischangedoesnotincreasetheprobability orconsequences ofanaccident. |
| | Thischangesdoesnotcreateanewordifferent accident. |
| | Therefore, anosignificant hazardsfindingiswarranted fortheproposedchanges. |
| 1p~04i4}} | | 1p~04i4}} |
Proposed Tech Specs Reducing Requirement for Low Pressurizer Water Level from 12 to 10.6% & Changing P-10 Permissive from 10 to 8% Power| ML17309A323 |
| Person / Time |
|---|
| Site: |
Ginna  |
|---|
| Issue date: |
01/19/1984 |
|---|
| From: |
ROCHESTER GAS & ELECTRIC CORP. |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML17309A321 |
List: |
|---|
| References |
|---|
| NUDOCS 8401250282 |
| Download: ML17309A323 (8) |
|
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|---|
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Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants.
ML17264A9391997-07-0707 July 1997
Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev
ML17264A9341997-07-0101 July 1997
to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624
ML17264A9461997-06-20020 June 1997
to Inservice Insp (ISI) Program.
ML17264A9241997-06-0303 June 1997
Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection
ML17311A0471997-05-22022 May 1997
Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr
ML17264A8671997-04-24024 April 1997
Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements
1999-06-28
[Table view] |
Text
Attachment; ARemove3.1-4b3.1-4e3.5-3Insert3;1-4b3.1-4e3.1-4f3.5-38401250282840119,',"
PDRADQCK05000244.,'
"".PDR 3.1.1.5Pressurizer Wheneverthereactorisathotshutdownorcriticalthepressurizer shallhaveatleast100kwofheatersoperableandawaterlevelmaintained between10.6%and87%oflevelspan.Ifthepressurizer isinoperable duetoheaterorwaterlevel,restorethepressurizer tooperablestatuswithin6hrs.orhavetheRHRsysteminoperation withinanadditional 6hrs.,Bases:Theplantisdesignedtooperatewithallreactorcoolantloopsinoperation andmaintaintheDNBRabove1.30duringallnormal3.1-4bChangeNo.ggAmendment No.gP,gg,jfg>PROPOSED Temperature requirements forthesteamgenerator correspond withmeasuredNDTfortheshellandallowable thermalstressesinthetubesheet.Eachofthepressurizer codesafetyvalvesisdesignedtorelieve288,000lbs.perhr.ofsaturated steamatthevalvesetpoint.
Below350Fand350psiginthereactorcoolantsystem,the0residualheatremovalsystemcanremovedecayheatandtherebyIIcontrolsyst'mtemperature andpressure.
Ifnoresidualheatwereremovedbyanyofthemeansavailable, theamountofsteamwhichcouldbegenerated atsafetyvalvereliefpressurewouldbelessthanhalfthevalves'apacity.
Onevalve,therefore, providesadequatedefenseagainstoverpressurization.
Thepoweroperatedreliefvalves(PORVs)operatetorelieveRCSpressurebelowthesettingofthepressurizer codesafetyvalves.Thesereliefvalveshaveremotelyoperatedblockvalvestoprovideapositiveshutoffcapability shouldareliefvalvebecomeinoper-able.Theelectrical powerforboththereliefvalvesandtheblockvalvesiscapableofbeingsuppliedfromanemergency powersourcetoensuretheabilitytosealthispossibleRCSleakagepath.Therequirement that100kwofpressurizer heatersandtheirassociated controlsbecapableofbeingsuppliedelectrical powerfromanemergency busprovidesassurance thattheseheaterscanbeenergized duringoss ofoffsitepowercondition tomaintainnaturalcirculation athotshutdownandduring3.1-4eAmendment No.gP,gg,PROPOSED cooldown.
Thepressurizer lowlevellimitof10.6%is"the(3)levelbelowwhichtheheatersarede-energized topreventdamage.References (1)FSARSection14.1.6(2)FSARSection7.2.3(3)LetterfromL.D.White,Jr.toD.L.Ziemann,USNRC,datedOctober17,19793.1-4fPROPOSED TABLE3.5-1INSTRUMENT OPERATION CONDITIONS Page1of2NO.FUNCTIONAL UNITNO.ofMIN.MIN.NO.ofCHANNELSOPERABLEDEGREEOFCHANNELSTOTRIP***CHANNELS'REDUNDANCY PERMISSIBLE BYPASSCGNDITIONS 6OPERATORACTIONIFCONDITIONS OFCOLUMN3OR5CANNOTBEMET1.Manual2.NuclearFluxPowerRangelowsettinghighsetting3.NuclearFluxIntermediate Range222of4pawerrangechannelsgreaterthan8%F.P.(lawsettingonly)2of4powerrangechannelsgreaterthan8%F.P.MaintainhotshutdawnMaintainhotshutdawnMaintainhotshutdawn.
Note14.NuclearFluxSourceRange5.Overtemperature T1of2intermediate Maintainhotrangechygnelsgreatershutdown.
Notethan10amps.=1Maintainhotshutdown6.Overpawer
-TCOs7OQMgU~8.HiPressurizer PressureZawPressurizer PressureMaintainhotshutdawnMaintainhotshutdownMaintainhotshutdownPressurizer-Hi WaterLevelMaintainhotshutdawnLawFlowinoneloop(>50%F.P.)LowFlowbothloops(10-50%F.P.)3/loop2/loop(anyloop)3/loop2/loop(anyloop)MaintainhotshutdownMaintainhotshutdown Attachment BThecurrentspecification onpressurizer waterlevelstatesthatthepressurizer levelshallbemaintained between12and87%.Theupperlimitisbasedonahighleveltripsetpointwithsufficient margintoaccountforreference legheatup.Thereisnobasisforthe12%lowerlimit.Sincelowpressurizer heatersarede-energized at10.6%,amoreappropriate valuewouldbe10.6%.TheP-10permissive allowsmanualblockingoftheinter-mediaterangerodstop,theintermediate rangehighfluxtrip,andlowsetpointofthepowerrangehighfluxtripabove10%power.Thesetripsareusedtomitigatetheconsequences ofarodwith-drawaltransient fromsubcritical.
TheproposedTechnical Specification changewouldallowtheabovetripstobebypassed(blocked) at8%power.Thischangeisnecessary becauseP-7permissive isrequiredat8.5%power.SinceoneoftheinputstoP-7comesfromthesamepowerrangebistablethatsuppliesP-10,P-10mustbeactuatedat8%powertosatisfy'.
therequirements forP-7.P-7automatically unblocksthefollow-.ingreactortrips:2looplowflow,reactorcoolantpumpbusundervoltage, reactorcoolantpumpbusunderfrequency, pressurizer lowpressure, andturbinetripwithP-9.Thesetripsareassociated withthe130MWwhichistheupperlimitofheatremovalwhileonnaturalcirculation.
Theonlytransient analysiswhichusesthistripisaslowrodwithdrawal.
(Borondilutionisboundedbytheslowrodwithdrawal.)
TheonlyeffectofreducingP-10to8%wouldbethatarodwithdrawal accident(RWA)startingfrom8%wouldbeterminated byhighfluxandovertemperature Tversustheintermediate andreducedhighpowertrips.Anevaluation performed ontheRWAstartingfrom8%and10%forvariousreactivity insertion ratesshowsapproximately thesameDNBRwhentheRWAisinitiated from8%versus10%power.Further,thereissubstantial marginbetweentheDNBRforaRWAfrom10%andthelimitingRWAfrom100%power.TheDNBRforaRWAstartingfrom8%willalsobegreaterthantheDNBRforthelimitingRWAstartedfrom100%power.Therefore, reducingP-10to8%hasnegligible effectontheGinnaSafetyAnalysisandtheminimumDNBRforall..RWAsisunchanged.
Attachment CInaccordance with10CFR50.91,thesechangestotheTechnical Specifications havebeenevaluated againstthreecriteriatodetermine iftheoperation ofthefac'ility inaccordance withtheproposedamendment would:l.involveasignificant, increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated; or3.involveasignificant reduction inamarginofsafety.Asoutlinedbelow,Rochester GasandElectricsubmitsthattheissuesassociated withthisamendment requestareoutsidethecriteriaof10CFR50.91,andtherefore, anosignificant hazardsfindingiswarranted.
Theproposedchangewouldreducethelowerpressurizer level'.limitfrom12to10.6%.Thisdoesnotincreasetheprobability o'consequences ofanaccident.
Thisdoesnotcreateanewordifferent accident.
Thisdoesnotreduceasafetymargin.TheproposedchangealsoreducestheP-10setpointfrom10to8%.Theevaluation doneshowsthatforthelimitingaccidents, thesafetymarginisnotsignificantly reduced.Thischangedoesnotincreasetheprobability orconsequences ofanaccident.
Thischangesdoesnotcreateanewordifferent accident.
Therefore, anosignificant hazardsfindingiswarranted fortheproposedchanges.
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